TY  - JOUR
AB  - A global intercomparison study was conducted to measure the thoron (220Rn) exhalation rate from two building materials, with participation from five European laboratories and three Asian laboratories. The test samples—phosphogypsum and unfired clay—were circulated among the laboratories using a sequential proficiency testing scheme. The assigned values and their uncertainties were determined through recommended robustness analysis. For comparison, the classical method, which uses the arithmetic mean of all participants' results, was also applied. Individual measurement results were evaluated for bias, precision, and proficiency in accordance with ISO 13528:2022. The assigned exhalation rates were (0.39 ± 0.15) Bq m−2 s−1 for phosphogypsum and (0.53 ± 0.15) Bq m−2 s−1 for unfired clay. Z-scores were below 3 for seven of the nine methods used. Bias (Rb) and precision (P) parameters were within 50 %, except in one case. Laboratories provided details on Type A and Type B uncertainties, revealing that detector calibration uncertainty was the dominant factor in most cases. These findings underscore the need for more robust calibration methods to improve the accuracy of thoron measurements. The development of a harmonised standard would greatly enhance the consistency of thoron exhalation rate measurements. Such a standard should provide guidance on detector calibration, as well as key factors such as climate conditions during sample preparation and testing, procedures for determining exhalation rates and their uncertainties, and considerations for material aging and spatial variations.
AU  - de With, G.*
AU  - Venoso, G.*
AU  - Maiorana, A.*
AU  - Di Carlo, C.*
AU  - Meisenberg, O.*
AU  - Guo, Q.*
AU  - Janik, M.*
AU  - Nugraha, E.D.*
AU  - Bobbo, O.M.*
AU  - Kranrod, C.*
AU  - Hosoda, M.*
AU  - Tokonami, S.*
AU  - Sahoo, B.K.*
AU  - Kanse, S.D.*
AU  - Tschiersch, J.
C1  - 74906
C2  - 57659
CY  - The Boulevard, Langford Lane, Kidlington, Oxford Ox5 1gb, England
TI  - Thoron exhalation rate measurement – findings from a large worldwide intercomparison study.
JO  - Radiat. Meas.
VL  - 187
PB  - Pergamon-elsevier Science Ltd
PY  - 2025
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Computational dosimetry using Monte Carlo radiation transport simulations was applied for the 2019 European Radiation Dosimetry Group (EURADOS) and Running the European Network of Biological and retrospective Physical dosimetry (RENEB) field test, an exercise of retrospective dosimetry techniques for a realistic small-scale radiological accident. The simulations were performed at four institutes, using different codes and computerized anthropomorphic phantoms. Four exposure scenarios using Ir-192 were modeled: relatively homogeneous in a predominantly AP direction, heterogeneous in a predominantly anterior-posterior (AP) and left-lateral (LLAT) direction, and partially shielded. The items for dosimetry, such as mobile phones, blood tubes, and surface dosimeters, were designed and located based on the experimental pictures. Absorbed doses of dosimeters, such as thermoluminescence dosimeter (TLD), optically stimulated luminescence dosimeters (OSLD), radio-photoluminescence dosimeters (RPLD), and display glasses, inside and outside the phantoms were calculated and compared to the measured doses. In addition, photon energy spectra were calculated at different locations to correct the energy responses of the materials. The simulation results from the four institutes showed agreement with each other, showing an average relative difference of less than 14%. The Pearson's R-values for the linear fitting of the measured and calculated data ranged from 0.95965 to 0.68714, depending on the exposure scenario and institutes. Finally, the accuracy and limitations of the calculation techniques for the given exposure structures are discussed.
AU  - Kim, H.*
AU  - Kim, M.C.*
AU  - Hoey, O.V.*
AU  - Eakins, J.S.*
AU  - Yu, H.*
AU  - Lee, H.*
AU  - Discher, M.*
AU  - Lee, J.*
AU  - Waldner, L.*
AU  - Woda, C.
AU  - Trompier, F.*
AU  - Bassinet, C.*
AU  - Sholom, S.*
AU  - McKeever, S.W.S.*
AU  - Ainsbury, E.A.*
C1  - 72495
C2  - 56589
CY  - The Boulevard, Langford Lane, Kidlington, Oxford Ox5 1gb, England
TI  - Monte Carlo dosimetry for a EURADOS WG 10 and RENEB field test of retrospective dosimetry techniques in realistic exposure scenarios.
JO  - Radiat. Meas.
VL  - 180
PB  - Pergamon-elsevier Science Ltd
PY  - 2025
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Dose conversion coefficients attempt to harmonize the material-, location-, and exposure-dependent results from retrospective dosemeters. The issues and uncertainties arising from dose conversion are explored within the framework of an interlaboratory comparison exercise in which mobile phones were positioned around anthropomorphic phantoms and exposed to non-uniform photon fields, with the glass and resistors they contain employed as fortuitous dosemeters. The difficulties of adopting pre-calculated tables of generic conversion coefficients are evaluated first, and then compared against those arising through the use of bespoke data derived by Monte Carlo modelling, and also against not converting the doses measured by the phones. It is seen that the different subjective choices that users might make when selecting ‘optimal’ generic data can lead to a significant source of uncertainty (up to around 70 %), though may be improved (to around 30 %) by appropriate quality controls. Use of generic coefficients typically led to over-estimates of the organ doses: an average discrepancy of ca. a factor of 2 was found, but this is still better than the factor of around 3 observed when no conversion coefficients were applied. Use of bespoke conversion factors led to the best estimates of organ doses, although they still over-estimated by approximately 1.5 on average, and an uncertainty of around 20 % was associated with generating their values. Overall, applying bespoke conversion data improves but does not guarantee correct dose categorization of individuals, with the inconsistences in the measured results found generally to be the limiting factor in obtaining accurate dose assessments.
AU  - Eakins, J.*
AU  - Discher, M.*
AU  - Kim, H.*
AU  - Kim, M.C.*
AU  - Lee, H.*
AU  - Lee, J.*
AU  - van Hoey, O.*
AU  - Yu, H.*
AU  - Ainsbury, E.*
AU  - Bassinet, C.*
AU  - McKeever, S.W.S.*
AU  - Sholom, S.*
AU  - Trompier, F.*
AU  - Waldner, L.*
AU  - Woda, C.
C1  - 72166
C2  - 56397
TI  - Dose conversion in retrospective dosimetry: Results and implications from an inter-laboratory comparison featuring a realistic exposure scenario.
JO  - Radiat. Meas.
VL  - 179
PY  - 2024
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Beryllium Oxide (BeO) is a promising dosimetric material that is rapidly becoming an essential instrument in Optically Stimulated Luminescence (OSL) dosimetry applications. Despite the potential of BeO as a luminescence dosimeter, gaps remain in understanding how its Thermoluminescence (TL) and Optically Stimulated Luminescence (OSL) signals are connected. Our study aimed at examining Residual Thermoluminescence (R-TL) glow curves after various bleaching times to find an association between TL traps and OSL components across a wide range of doses, at 40 mGy and from 10 to 100 Gy. OSL decay curves and intensities of R-TL glow curves were fitted to either pure exponential decay functions or to stretched exponential decay functions, due to optical attenuation, to determine the OSL components and the bleaching decay rates of each TL peak, respectively. A good correlation between the decay rates of the OSL components and bleaching decay rates of each TL peak for both high and low-dose irradiations was found only for the model functions considering optical attenuation in the material. Taken together, this qualitative method helped to identify various traps, and results revealed a more consistent luminescence mechanism between TL and OSL signals than was previously assumed. Further support for the correlation between TL and OSL was derived from thermal stability studies of the OSL signal and from the dose response of the TL peaks and the OSL signal after different thermal pretreatments. Different bleaching models were discussed to define the appropriate one for BeO. These results may enhance our understanding of BeO as a dosimeter.
AU  - Kara, E.
AU  - Woda, C.*
C1  - 69070
C2  - 53843
CY  - The Boulevard, Langford Lane, Kidlington, Oxford Ox5 1gb, England
TI  - Correlation between thermoluminescence and optically stimulated luminescence signal in BeO.
JO  - Radiat. Meas.
VL  - 170
PB  - Pergamon-elsevier Science Ltd
PY  - 2024
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Measuring absorbed doses with high precision and accuracy for clinical applications using Optically Stimulated Luminescence (OSL) dosimeters can help to optimize treatment to patients. Beryllium Oxide (BeO) is a nearly tissue-equivalent material that has the potential to increase the applicability of OSL dosimetry in medical dosimetry, but there has been limited research into its characterization. We present here the characterization of BeO dosimeters in terms of annealing temperature and duration, the effect of preheat treatment on short-term fading, energy and angular dependence, and discuss possible errors in laboratory conditions by using the OSL technique. Shorter readoutof 30 s when using stimulation power of ∼30 mW cm2 is feasible but preheating then becomes necessary. The fading behavior of BeO was found to be dose-dependent in this case. Reproduciblity of an OSL measurement with repositioning of the dosimeter in the reader and for the short reaout times was found to be ∼1%. Energy response was close to the theoretical values, which agrees with some but differs from other published studies, indicating that the OSL efficiency might vary. The angular dependence presented the greatest uncertainty factor. In summary, BeO dosimeters have the potential to be used in clinical applications for dose evaluation. However, care should be taken while handling and applying an optimized measurement procedure is necessary due to the complex luminescence mechanism of the material.
AU  - Kara, E.
AU  - Woda, C.
C1  - 68172
C2  - 53615
CY  - The Boulevard, Langford Lane, Kidlington, Oxford Ox5 1gb, England
TI  - Further characterization of BeO detectors for applications in external and medical dosimetry.
JO  - Radiat. Meas.
VL  - 165
PB  - Pergamon-elsevier Science Ltd
PY  - 2023
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - An error was identified in the publication by Rabus et al. (2021) summarizing the results of a code comparison exercise organized by the European Radiation Dosimetry Group (EURADOS). In the exercise, the electron spectra emitted by a gold nanoparticle (GNP) in water under irradiation with a confined X-ray beam and the resulting energy deposition in spherical water shells around the GNP were to be determined. Spherical GNPs of 50 nm and 100 nm diameter and two X-ray spectra (50 kVp, 100 kVp) were considered. Photons were emitted from the source as a parallel beam with a circular cross-section whose diameter was 10 nm larger than the GNPs. The error was an incorrectly selected display option in the Origin program used to create Fig. 5 in Rabus et al. (2021). The figure shows energy spectra of electrons in a histogram-like display to illustrate that the data shown are average frequency densities in the intervals of the energy bins. In three of the four panels of Fig. 5, the data were presented in such a way that the energy indicating the energy bin was used as its lower limit, when in fact these energies were the centers of the energy bins. The corrected Fig. 5 is shown below. This error does not affect the conclusions of the paper, which remain unchanged. The authors apologize for any inconvenience.[Formula presented]
AU  - Rabus, H.*
AU  - Li, W.B.
AU  - Nettelbeck, H.*
AU  - Schuemann, J.*
AU  - Villagrasa, C.*
AU  - Beuve, M.*
AU  - di Maria, S.*
AU  - Heide, B.*
AU  - Poignant, F.*
AU  - Qiu, R.*
AU  - Rudek, B.*
C1  - 68466
C2  - 53891
CY  - The Boulevard, Langford Lane, Kidlington, Oxford Ox5 1gb, England
TI  - Corrigendum on H. Rabus et al. “Consistency checks of results from a Monte Carlo code intercomparison for emitted electron spectra and energy deposition around a single gold nanoparticle irradiated by X-rays” [Radiat. Meas. 147 (2021) 106637] (Radiation Measurements (2021) 147, (S1350448721001487), (10.1016/j.radmeas.2021.106637)).
JO  - Radiat. Meas.
VL  - 168
PB  - Pergamon-elsevier Science Ltd
PY  - 2023
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Purpose: This study investigates the influence of several Monte Carlo radiation transport codes and nuclear models on the simulation of secondary neutron spectra and its impact on calculating and measuring the neutron doses in proton therapy. Materials and methods: Three different multi-purpose Monte Carlo radiation transport codes (FLUKA, MCNPX, Geant4) were used together with different available nuclear models, to calculate secondary neutron energy spectra at various points inside a water tank phantom with PMMA walls using a 10 × 10 cm2 rectangular, mono-energetic proton beam (110 MeV, 150 MeV, 180 MeV, 210 MeV). Using Kerma approximation secondary neutron doses were calculated applying fluence-to-dose equivalent conversion coefficients in water. Moreover, the impact of varying spectra for electrochemically etched CR39 detector calibration was analyzed for different codes and models. Results: In distal positions beyond the Bragg peak, results show largest variations between the codes, which was up to 53% for the high energy neutron fluence at 16 cm from the Bragg peak of the 110 MeV proton beam. In lateral positions, the variation between the codes is smaller and for the total neutron fluence within 20%. Variation in the nuclear models in MCNPX was only visible for the proton beam energies of 180 and 210 MeV and modeling the high energy neutron fluence which reached up to 23% for 210 MeV at 11 cm lateral from the beam axis. Impact on neutron dose equivalent was limited for the different models used (<8%) while it was pronounced for the different codes (45% at 16 cm from the Bragg peak of the 110 MeV proton beam). CR39 calibration factors in lateral positions were on average varying 10% between codes and 5% between nuclear models. Conclusions: This study demonstrated a large impact on the neutron fluence spectra calculated by different codes while the impact of different models in MCNPX proved to be less prominent for the neutron modeling in proton therapy.
AU  - De Saint-Hubert, M.*
AU  - Farah, J.*
AU  - Klodowska, M.*
AU  - Romero-Expósito, M.T.*
AU  - Tymińska, K.*
AU  - Mares, V.
AU  - Olko, P.*
AU  - Stolarczyk, L.*
AU  - Trinkl, S.*
C1  - 63834
C2  - 51677
TI  - The influence of nuclear models and Monte Carlo radiation transport codes on stray neutron dose estimations in proton therapy.
JO  - Radiat. Meas.
VL  - 150
PY  - 2022
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - This paper summarizes the results of an intercomparison on the use of the ICRP Reference Computational Phantoms with radiation transport codes, which was organized by EURADOS working group 6. Three exercises are described: exposure to an anterior-posterior (AP) photon point source, exposure to an AP neutron point source, and exposure to two typical medical X-ray examinations. The three exercises received 17, 8 and 8 solutions, respectively. Participants originated from fifteen different countries, and used a wide range of Monte Carlo codes. Due to difficulties in defining the precise source location unambiguously in the exercise description, agreement to within ∼10% of the reference solution was considered satisfactory for a given participant's results. Although some participants provided initial solutions in good agreement with the reference solutions, differences of several tens of percent, or even several orders of magnitude, were exhibited for many of the others. Following feedback and suggestions from the organizers, revised solutions were submitted by some of the participants for the photon exercises; in general, agreement was improved. The overall observations from these three intercomparison exercises are summarized and discussed.
AU  - Huet, C.*
AU  - Eakins, J.*
AU  - Zankl, M.
AU  - Gómez-Ros, J.M.*
AU  - Jansen, J.*
AU  - Moraleda, M.*
AU  - Struelens, L.*
AU  - Akar, D.K.*
AU  - Borbinha, J.*
AU  - Brkić, H.*
AU  - Bui, D.K.*
AU  - Capello, K.*
AU  - Linh Dang, T.M.*
AU  - Desorgher, L.*
AU  - Di Maria, S.*
AU  - Epstein, L.*
AU  - Faj, D.*
AU  - Fantinova, K.*
AU  - Ferrari, P.*
AU  - Gossio, S.*
AU  - Hunt, J.*
AU  - Jovanovic, Z.*
AU  - Kim, H.S.*
AU  - Krstic, D.*
AU  - Le, N.T.*
AU  - Lee, Y.K.*
AU  - Murugan, M.*
AU  - Nadar, M.Y.*
AU  - Nguyen, N.Q.*
AU  - Nikezic, D.*
AU  - Patni, H.K.*
AU  - Santos, D.S.*
AU  - Tremblay, M.*
AU  - Triviño, S.*
AU  - Tymińska, K.*
C1  - 63818
C2  - 51567
TI  - Monte Carlo calculation of organ and effective doses due to photon and neutron point sources and typical X-ray examinations: Results of an international intercomparison exercise.
JO  - Radiat. Meas.
VL  - 150
PY  - 2022
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Organized by Working Group 6 “Computational Dosimetry” of the European Radiation Dosimetry
       Group (EURADOS), a group of intercomparison exercises was conducted in 
      which participants were asked to solve predefined problems in 
      computational dosimetry. The results of these comparisons were published
       in a series of articles in this virtual special issue of Radiation 
      Measurements. This paper reviews the experience gained from the various 
      exercises and highlights the resulting conclusions for future exercises,
       as well as regarding the state of the art and the need for development 
      in terms of quality assurance for computational dosimetry techniques.
AU  - Rabus, H.*
AU  - Zankl, M.
AU  - Gómez-Ros, J.M.*
AU  - Villagrasa, C.*
AU  - Eakins, J.*
AU  - Huet, C.*
AU  - Brkić, H.*
AU  - Tanner, R.*
C1  - 65912
C2  - 52490
TI  - Lessons learnt from the recent EURADOS intercomparisons in computational dosimetry.
JO  - Radiat. Meas.
VL  - 156
PY  - 2022
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - In this study, the Geant4 Monte Carlo toolkit was used to simulate energy spectra of neutrons from secondary cosmic radiation at mountain altitudes for the Environmental Research Station "Schneefernerhaus" at the Zugspitze mountain, Germany (2660 m a.s.l.) and for Sphinx astronomical observatory at the Jungfraujoch, Switzerland (3585 m a.s.l.). Simulations were performed with different intra-nuclear cascade models available in Geant4, and the results were compared with those of measurements that had been performed at both locations by means of an Extended-Range Bonner Sphere Spectrometer. Measurement conditions were quite different for both locations - at Schneefernerhaus the measurements had been performed on the flank of a hill in March 2018 with much snow, while at Jungfraujoch the measurements had been performed on top of a steep local hill in September 2018 with much less snow. Despite these differences, agreement between measurement and simulation was reasonable at both locations, especially at neutron energies greater than 20 MeV where the (unknown) hydrogen content of the environment did not influence the neutron fluence much (i.e., results from simulations were 6-22% lower than those from the measurements for the Schneefernerhaus, and were 22-29% lower for Jungfraujoch, depending on intra-nuclear model used in the simulations). The agreement was less favorable for lower energies, where environmental hydrogen (e.g., snow cover, soil moisture) is known to influence the shape of the neutron energy spectrum, because the real conditions of the snow accumulation close to the location of the measurements were not known and, therefore, a detailed description of the real hydrogen environment in the simulations was not possible. When the results simulated using different intra-nuclear cascade models were compared with each other, agreement was found within +/- 5%, +/- 15%, +/- 20%, and +/- 20%, for cascade, evaporation, epithermal and thermal neutrons, respectively. While the latter results are consistent with those of simulations and measurements at the CERN EU High-Energy Reference Field (CERF) facility published recently, a detailed sensitivity analysis of the influence of environmental hydrogen on neutron energy spectra is required before a final quantitative comparison of measurements and simulations can be made. This sensitivity analysis is presently under way. It is concluded that simulation of energy spectra of neutrons from secondary cosmic rays close to the atmosphere-lithosphere interface, validated by the spectrometer measurements, showed differences of less than 30%, for neutron energies greater than 20 MeV, whatever intra-nuclear cascade model was used in the simulations.
AU  - Brall, T.
AU  - Mares, V.
AU  - Bütikofer, R.*
AU  - Rühm, W.
C1  - 62363
C2  - 50705
CY  - The Boulevard, Langford Lane, Kidlington, Oxford Ox5 1gb, England
TI  - Assessment of secondary neutrons from galactic cosmic rays at mountain altitudes-Geant4 simulations and ground-based measurements of neutron energy spectra.
JO  - Radiat. Meas.
VL  - 144
PB  - Pergamon-elsevier Science Ltd
PY  - 2021
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - The radiological incident in Cochabamba (Bolivia, 2002), where members of the general public where exposed to an unshielded Ir-192 radiation source whilst traveling on a bus was replicated here in an attempt to asses and evaluate emerging retrospective dosimetry methodologies using objects of daily life, that are either carried on or close to the human body or can be found in the vicinity of an individual. For this purpose an accidental exposure was simulated under controlled conditions in a secured area and an unshielded radioactive source was placed in the cargo compartment of a bus resembling a Radiological Exposure Device (RED). Water canisters and anthropomorphic phantoms were placed at selected seats on the bus and equipped with personal objects (mobile phones, chip cards) that had reference dosimeters attached to them. At one seat position, additional salt dosimeters and dental ceramics in the phantom were also tested. Two types of 8 h exposures were conducted: one with a source activity similar to the one in Cochabamba (0.65 TBq) and one with a stronger source (1.5 TBq) in order to have more samples with absorbed doses above the detection limit of the different methods. For 43 out of 61 resistor and glass samples from mobile phones, measured doses agreed within error limits with reference doses, but for some materials more research is needed for a more reliable application. In 13 cases outliers with a significant dose over- or underestimation were observed, 10 of these could be identified by combining the results of at least three dose assays. The field test thus evaluated the potential and limitation of retrospective dosimetry using personal objects and demonstrated the importance of using a multi-dosimeter approach to increase robustness of the method.
AU  - Discher, M.
AU  - Woda, C.
AU  - Ekendahl, D.*
AU  - Rojas-Palma, C.*
AU  - Steinhäusler, F.*
C1  - 61994
C2  - 50422
CY  - The Boulevard, Langford Lane, Kidlington, Oxford Ox5 1gb, England
TI  - Evaluation of physical retrospective dosimetry methods in a realistic accident scenario: Results of a field test.
JO  - Radiat. Meas.
VL  - 142
PB  - Pergamon-elsevier Science Ltd
PY  - 2021
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Monte Carlo modelling has been performed to simulate aspects of the CATO exercise, which recreated the exposure of individuals on a bus to an Ir-192 point source. The modelling allowed a comparison and check of the measured data provided in (Rojas-Palma et al., 2020; Discher et al., 2021), and an investigation into the dose conversion coefficients that are required in order to use fortuitous dosemeters as indicators of absorbed doses to individuals; a conversion factor of 0.22 ± 0.01 was found to be appropriate to relate the phone dose to the average organ dose. The modelling also allowed some of the parameters of the experiment to be varied, and their impacts explored. In general, measured and modelled data agreed acceptably, with similar average doses and broadly similar variations in the results as a function of organ type.
AU  - Discher, M.
AU  - Eakins, J.*
AU  - Woda, C.
AU  - Tanner, R.*
C1  - 62620
C2  - 50881
CY  - The Boulevard, Langford Lane, Kidlington, Oxford Ox5 1gb, England
TI  - Translation of the absorbed dose in the mobile phone to organ doses of an ICRP voxel phantom using MCNPX simulation of an Ir-192 point source.
JO  - Radiat. Meas.
VL  - 146
PB  - Pergamon-elsevier Science Ltd
PY  - 2021
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - A thermally assisted optically stimulated luminescence protocol for the use of display glass samples from mobile phones as a fortuitous dosimeter was developed. Glass samples from 16 different mobile phones from the Samsung Galaxy series were used. The protocol consists of a prebleach with LEDs of 470 nm for 500 s and an OSL reading for 500 s at an elevated temperature. The decay curves were measured at different temperatures from 100 to 400 °C in an interval of 50 °C. A significant baseline increase in the decay curves was observed above 350 °C. For the TA-OSL below 300 °C, the dose response from 10 mGy to 10 Gy was linear and the signals were reproducible within 5% for six repeated readings. Compared with the residual thermoluminescence after an isothermal reading, the TA-OSL protocol showed lower zero doses at the given temperature. By increasing the temperature of the TA-OSL protocol from 100 to 300 °C, the minimum detectable dose increased from 17 to 70 mGy, but the fading rate reduced from 64% to 36% after 41 days from irradiation. In the optical stability test, strong reductions in TA-OSL signals were observed after exposures up to 1000 s with several light sources, and it was found that violet LEDs are more effective than blue LEDs for bleaching. As a result, the TA-OSL protocols investigated showed some improvements in terms of the lower minimum detectable doses and reduced fading rates compared with the prebleached thermoluminescence protocol.
AU  - Kim, H.*
AU  - Discher, M.*
AU  - Kim, M.C.*
AU  - Woda, C.
AU  - Lee, J.*
C1  - 62475
C2  - 50791
CY  - The Boulevard, Langford Lane, Kidlington, Oxford Ox5 1gb, England
TI  - Thermally assisted optically stimulated luminescence protocol of mobile phone substrate glasses for accident dosimetry.
JO  - Radiat. Meas.
VL  - 146
PB  - Pergamon-elsevier Science Ltd
PY  - 2021
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Glass displays from mobile phones show a characteristic thermoluminescence (TL) signal after the exposure to ionizing radiation. Therefore they can be used as accident and emergency dosimeters. This paper carries out quantitative analysis of such TL signals by using several standard methods of analyzing luminescence signals. Application of the initial rise method to 120 TL glow curves obtained by the Tmax-Tstop method, shows that the TL signals can be described by a quasi-continuous distribution of energies in the range of E=0.8-1.5 eV. The shape of the TL signals was simulated by using five Gaussian trap energy distributions centered at five discrete activation energy values and a single frequency factor s. The result of the simulations were in a good quantitative agreement with all the experimental TL glow curves. Two additional experiments investigating the variation of the TL signal with the heating rate, and studying the fading of the TL signal at room temperature over long periods of time, showed that this material exhibits the well known anomalous heating rate effect, and anomalous fading of the TL signal. The results of these two experiments demonstrate that the luminescence mechanism in this dosimetric material is rather complex, and that additional recombination pathways affect the luminescence process during a TL measurement.
AU  - Pagonis, V.*
AU  - Woda, C.
AU  - Discher, M.*
C1  - 62374
C2  - 50851
CY  - The Boulevard, Langford Lane, Kidlington, Oxford Ox5 1gb, England
TI  - Quantitative analysis of thermoluminescence signals of glass displays from mobile phones.
JO  - Radiat. Meas.
VL  - 146
PB  - Pergamon-elsevier Science Ltd
PY  - 2021
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Organized by the European Radiation Dosimetry Group (EURADOS), a Monte Carlo code intercomparison exercise was conducted where participants simulated the emitted electron spectra and energy deposition around a single gold nanoparticle (GNP) irradiated by X-rays. In the exercise, the participants scored energy imparted in concentric spherical shells around a spherical volume filled with gold or water as well as the spectral distribution of electrons leaving the GNP. Initially, only the ratio of energy deposition with and without GNP was to be reported. During the evaluation of the exercise, however, the data for energy deposition in the presence and absence of the GNP were also requested. A GNP size of 50 nm and 100 nm diameter was considered as well as two different X-ray spectra (50 kVp and 100 kVp). This introduced a redundancy that can be used to cross-validate the internal consistency of the simulation results. In this work, evaluation of the reported results is presented in terms of integral quantities that can be benchmarked against values obtained from physical properties of the radiation spectra and materials involved. The impact of different interaction cross-section datasets and their implementation in the different Monte Carlo codes is also discussed.
AU  - Rabus, H.*
AU  - Li, W.B.
AU  - Nettelbeck, H.*
AU  - Schuemann, J.*
AU  - Villagrasa, C.*
AU  - Beuve, M.*
AU  - di Maria, S.*
AU  - Heide, B.*
AU  - Klapproth, A.
AU  - Poignant, F.*
AU  - Qiu, R.*
AU  - Rudek, B.*
C1  - 62782
C2  - 51060
CY  - The Boulevard, Langford Lane, Kidlington, Oxford Ox5 1gb, England
TI  - Consistency checks of results from a Monte Carlo code intercomparison for emitted electron spectra and energy deposition around a single gold nanoparticle irradiated by X-rays.
JO  - Radiat. Meas.
VL  - 147
PB  - Pergamon-elsevier Science Ltd
PY  - 2021
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Radiation doses accumulated in ceramic or brick and assessed by thermoluminescence (TL) or optically stimulated luminescence (OSL) measurements are commonly used as a source of independent dosimetric information, helpful for validation of retrospective estimates of population exposures to anthropogenic radiation sources. This work systematically evaluates contributions to the cumulative dose in brick samples located at different heights in a wall from anthropogenic and natural radiation sources and provides data for quantification of the natural background component of the total dose in the brick derived in TL/OSL-measurements. Al- and Cu-cased thermoluminescence dosimeters (TLD) based on Al2O3:C are used to measure contemporary doses in brick walls as benchmarks and for validation of the dose reconstruction procedures. Correspondingly, doses in TLD and in brick in the same locations and under the same irradiation conditions are obtained by Monte Carlo simulations of radiation transport in realistic geometries. The data obtained in the simulations indicate that energy response of Al-cased dosimeters agrees better with the energy response of the brick than the response of Cu-cased TLD. The dosimetric data and relationships between doses in TLD and in brick are systematically derived for different locations in the wall and above the ground and used in other dose reconstruction studies with luminescence techniques.
AU  - Ulanowski, A.
AU  - Hiller, M.
AU  - Woda, C.
C1  - 60885
C2  - 49720
CY  - The Boulevard, Langford Lane, Kidlington, Oxford Ox5 1gb, England
TI  - Absorbed doses in bricks and TL-dosimeters due to anthropogenic and natural environmental radiation sources.
JO  - Radiat. Meas.
VL  - 140
PB  - Pergamon-elsevier Science Ltd
PY  - 2021
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - To account for an enhancement of the absorbed dose to both active marrow and endosteum due to secondary electrons generated in bone trabeculae and depositing energy in adjacent marrow tissues, a specific method for bone dosimetry has been developed and introduced in ICRP Publication 116 for photons and neutrons. In a recent intercomparison exercise on the usage of the ICRP/ICRU adult reference computational phantoms carried out by EURADOS WG6, it turned out that many participants found it difficult to correctly apply the bone dosimetry method as recommended by the ICRP. The purpose of this article is, therefore, to provide practical guidance and technical hints for incorporating the ICRP bone dosimetry method into various types of radiation transport codes.
AU  - Zankl, M.
AU  - Eakins, J.*
AU  - Gomez Ros, J.M.*
AU  - Huet, C.*
C1  - 62536
C2  - 50810
CY  - The Boulevard, Langford Lane, Kidlington, Oxford Ox5 1gb, England
TI  - The ICRP recommended methods of red bone marrow dosimetry.
JO  - Radiat. Meas.
VL  - 146
PB  - Pergamon-elsevier Science Ltd
PY  - 2021
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - The European Radiation Dosimetry Group, EURADOS, has organised an intercomparison study on the usage of the ICRP/ICRU voxel reference computational phantoms together with radiation transport codes. Voluntary participants have been invited to solve specific tasks and provide solutions to the organisers before a certain deadline. The tasks to be solved are of practical interest in occupational, environmental and medical dosimetry. The aims of this training activity were to investigate if the phantoms have been correctly implemented in the radiation transport codes and to give the participants the opportunity to check their own calculations against quality-assured master solutions and improve their approach, if needed.
AU  - Zankl, M.
AU  - Eakins, J.*
AU  - Gómez Ros, J.M.*
AU  - Huet, C.*
AU  - Jansen, J.*
AU  - Moraleda, M.*
AU  - Reichelt, U.*
AU  - Struelens, L.*
AU  - Vrba, T.*
C1  - 62173
C2  - 50556
CY  - The Boulevard, Langford Lane, Kidlington, Oxford Ox5 1gb, England
TI  - EURADOS intercomparison on the usage of the ICRP/ICRU adult reference computational phantoms.
JO  - Radiat. Meas.
VL  - 145
PB  - Pergamon-elsevier Science Ltd
PY  - 2021
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - EURADOS Working Group 6 has organized an intercomparison exercise on the use of the ICRP Reference Computational Phantoms with radiation transport codes. This paper summarizes the results of a specific task from the intercomparison exercise modelling internal radiation sources. The quantities to be calculated were absorbed fractions and specific absorbed fractions for monoenergetic photon and electron sources as well as S-values for two radionuclides in four source organs. Twelve participants from eleven countries participated in this specific task using the Monte Carlo radiation transport codes FLUKA, Geant4, the MCNP code family, PenEasy, TRIPOLI-4 and VMC. Although some participants provided initial solutions in good agreement with the master solution evaluated by the organizers, differences of factors or even orders of magnitude were also found. Following feedback from the organizer, most participants submitted revised solutions that were mostly in better agreement with the master solution, although this was not always the case. Some initial and revised results are discussed in detail in this paper, and the reasons of mistakes are described as far as they were revealed by the participants. A full account of all results is presented in specific annexes as supplemental material.
AU  - Zankl, M.
AU  - Gomez Ros, J.M.*
AU  - Moraleda, M.*
AU  - Reichelt, U.*
AU  - Akar, D.K.*
AU  - Borbinha, J.*
AU  - Desorgher, L.*
AU  - di Maria, S.*
AU  - EL Bakkali, J.*
AU  - Fantínová, K.*
AU  - Ferrari, P.*
AU  - Gossio, S.*
AU  - Hunt, J.*
AU  - Jovanovic, Z.*
AU  - Kim, H.S.*
AU  - Krstic, D.*
AU  - Lee, Y.K.*
AU  - Nadar, M.Y.*
AU  - Nikezic, D.*
AU  - Patni, H.K.*
AU  - Murugan, M.*
AU  - Triviño, S.*
C1  - 63244
C2  - 51258
CY  - The Boulevard, Langford Lane, Kidlington, Oxford Ox5 1gb, England
TI  - Monte Carlo calculation of organ dose coefficients for internal dosimetry: Results of an international intercomparison exercise.
JO  - Radiat. Meas.
VL  - 148
PB  - Pergamon-elsevier Science Ltd
PY  - 2021
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Aircraft crew are one of the groups of radiation workers which receive the highest annual exposure to ionizing radiation. Validation of computer codes used routinely for calculation of the exposure due to cosmic radiation and the observation of nonpredictable changes in the level of the exposure due to solar energetic particles, requires continuous measurements onboard aircraft. Appropriate calibration of suitable instruments is crucial, however, for the very complex atmospheric radiation field there is no single reference field covering all particles and energies involved. Further intercomparisons of measurements of different instruments under real flight conditions are therefore indispensable.In November 2017, the REFLECT (REsearch FLight of EURADOS and CRREAT) was carried out. With a payload comprising more than 20 different instruments, REFLECT represents the largest campaign of this type ever performed. The instruments flown included those already proven for routine dosimetry onboard aircraft such as the Liulin Si-diode spectrometer and tissue equivalent proportional counters, as well as newly developed detectors and instruments with the potential to be used for onboard aircraft measurements in the future. This flight enabled acquisition of dosimetric data under well-defined conditions onboard aircraft and comparison of new instruments with those routinely used.As expected, dosimeters routinely used for onboard aircraft dosimetry and for verification of calculated doses such as a tissue equivalent proportional counter or a silicon detector device like Liulin agreed reasonable with each other as well as with model calculations. Conventional neutron rem counters underestimated neutron ambient dose equivalent, while extended-range neutron rem counters provided results comparable to routinely used instruments. Although the responses of some instruments, not primarily intended for the use in a very complex mixed radiation field such as onboard aircraft, were as somehow expected to be different, the verification of their suitability was one of the objectives of the REFLECT. This campaign comprised a single short flight. For further testing of instruments, additional flights as well as comparison at appropriate reference fields are envisaged. The REFLECT provided valuable experience and feedback for validation of calculated aviation doses.
AU  - Ambrožová, I.*
AU  - Beck, P.*
AU  - Benton, E.R.*
AU  - Billnert, R.*
AU  - Bottollier-Depois, J.F.*
AU  - Caresana, M.*
AU  - Dinar, N.*
AU  - Domanski, S.*
AU  - Gryziński, M.A.*
AU  - Kákona, M.*
AU  - Kolros, A.*
AU  - Krist, P.*
AU  - Kuć, M.*
AU  - Kyselová, D.*
AU  - Latocha, M.*
AU  - Leuschner, A.*
AU  - Lillhök, J.*
AU  - Maciak, M.*
AU  - Mares, V.
AU  - Murawski, Ł.*
AU  - Pozzi, F.*
AU  - Reitz, G.*
AU  - Schennetten, K.*
AU  - Silari, M.*
AU  - Šlegl, J.*
AU  - Sommer, M.*
AU  - Štěpán, V.*
AU  - Trompier, F.*
AU  - Tscherne, C.*
AU  - Uchihori, Y.*
AU  - Vargas, A.*
AU  - Viererbl, L.*
AU  - Wielunski, M.
AU  - Wising, M.*
AU  - Zorloni, G.*
AU  - Ploc, O.*
C1  - 59904
C2  - 49077
CY  - The Boulevard, Langford Lane, Kidlington, Oxford Ox5 1gb, England
TI  - REFLECT - Research flight of EURADOS and CRREAT: Intercomparison of various radiation dosimeters onboard aircraft.
JO  - Radiat. Meas.
VL  - 137
PB  - Pergamon-elsevier Science Ltd
PY  - 2020
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - A new BeOSL eye lens dosemeter for integration in radiation protection glasses has been investigated in laboratory tests on an Alderson head phantom. Several dosemeter positions on an unshielded Alderson phantom were exposed in the primary x-ray beam. They were then compared to dosemeters shielded by radiation protection glasses, including a new model (MAVIG BR330) featuring a mechanical interface for the dosemeter. Primary goals were to evaluate the dose reduction for several types of glasses and geometries, as well as to confirm optimal dosemeter position for evaluation of the dose to the eye lens. Results show that radiation protection glasses lower the dose to the eye lens and thus should be worn at all times. Furthermore, they confirm the choice of the measuring position behind the lateral shielding next to the eye closer to the radiation source. However, we also show that small changes in geometry can have a large effect on both dosimetry and protection properties of the glasses. Finally, the results are extended to a wider energy range with data from Monte Carlo Simulations.
AU  - Bandalo, V.
AU  - Figel, M.
AU  - Greiter, M.
AU  - Brönner, J.
AU  - Kleinau, P.
AU  - Haninger, T.
AU  - Strobel, I.
AU  - Mende, E.
AU  - Scheubert, P.*
AU  - Eßer, R.*
AU  - Furlan, M.*
AU  - Schmid, M.*
AU  - Hödlmoser, H.
C1  - 57859
C2  - 47707
CY  - The Boulevard, Langford Lane, Kidlington, Oxford Ox5 1gb, England
TI  - Performance of the BeOSL eye lens dosemeter with radiation protection glasses.
JO  - Radiat. Meas.
VL  - 131
PB  - Pergamon-elsevier Science Ltd
PY  - 2020
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - In the present paper Geant4 Monte Carlo simulations of the CERN-EU high-energy Reference Field (CERF) facility in Geneva, Switzerland, are presented. At this facility a neutron field with a broad energy distribution from thermal energies up to GeV is available. To validate the simulated neutron fluences, the CERF neutron energy distribution was also measured with an extended range Bonner Sphere Spectrometer. Both measurements and simulations are compared against the official CERF reference distributions that were calculated with the Monte Carlo code FLUKA. It turned out that the differences between the total neutron fluences simulated with Geant4 and those measured were less than 41%, depending on the measurement position. While the total fluences simulated with the Geant4 Binary INC model (QGSP_BIC_HP) and the corresponding FLUKA reference values were up to 41% lower than those measured, the total fluences simulated with the Geant4 Bertini INC model (QGSP_BERT_HP) overestimated (up to 27%) the experimental results. As compared to the measured ambient dose equivalent H*(10), similar differences were observed with H*(10) values higher by about 29% for the Geant4 Bertini INC simulations and lower by about 48% for the Geant4 Binary INC and FLUKA simulations.
AU  - Brall, T.
AU  - Dommert, M.*
AU  - Rühm, W.
AU  - Trinkl, S.*
AU  - Wielunski, M.
AU  - Mares, V.
C1  - 58653
C2  - 48557
CY  - The Boulevard, Langford Lane, Kidlington, Oxford Ox5 1gb, England
TI  - Monte Carlo simulation of the CERN-EU High Energy Reference Field (CERF) facility.
JO  - Radiat. Meas.
VL  - 133
PB  - Pergamon-elsevier Science Ltd
PY  - 2020
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Phototransferred thermoluminescence (PTTL) of mobile phone display glass (category A) is systematically investigated to develop a robust measurement protocol for its emergency dosimeter usage after an incident with ionizing radiation. First, optimal readout parameters were defined by varying preheat temperature and holding time preceding violet exposure (405 nm). Next, the detection window of the PTTL measurement was adjusted to optimize the ratio between radiation-induced (RIS) and non-radiation-induced signals (nRIS) of the PTTL. Finally, the developed protocol determines PTTL after preheating to 400 degrees C and holding for 10 s was tested using the detection window centered at 340 nm. Dosimetric properties such as the PTTL reproducibility and dose response were investigated. PTTL signal stability tests showed that the violet PTTL signal originates from deeper and consequently more thermally stable traps. A signal loss of less than 10% after 10.6 days (254 h) storage was observed. Additionally, TL and PTTL spectra were recorded to investigate the luminescence emissions after beta and gamma irradiation and different UV exposures. PTTL emissions are similar to TL emission. Varying UV energy a qualitative comparison demonstrate that the RIS and nRIS PTTL signal intensities increase significantly with decreasing UV stimulation wavelength. In general, the developed PTTL protocol indicates better signal stability and thus some advantages over other techniques, however, further research is needed to test the potential of a new method for physical retrospective dosimetry.
AU  - Discher, M.*
AU  - Woda, C.
AU  - Lee, J.*
AU  - Kim, H.*
AU  - Chung, K.*
AU  - Lang, A.*
C1  - 58498
C2  - 48509
CY  - The Boulevard, Langford Lane, Kidlington, Oxford Ox5 1gb, England
TI  - PTTL characteristics of glass samples from mobile phones.
JO  - Radiat. Meas.
VL  - 132
PB  - Pergamon-elsevier Science Ltd
PY  - 2020
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - The Individual Monitoring Service (IMS) at the Helmholtz Zentrum Miinchen together with Dosimetrics GmbH has developed and characterized a new ring dosemeter for photon radiation for the measurement of H-p(0,07), based on BeOSL technology. This work describes the new finger ring dosemeter and provides data from Monte Carlo simulation and from the radiological characterization of the dosemeters according to IEC 62387, such as the energy and angular response functions of the dosemeter, its dose linearity and the coefficient of variation. Furthermore, the opacity of the dosemeter enclosure and light conditions for packing and unpacking of the detectors are addressed.
AU  - Hödlmoser, H.
AU  - Greiter, M.
AU  - Bandalo, V.
AU  - Brönner, J.
AU  - Haninger, T.
AU  - Emmerl, M.
AU  - Mende, E.
AU  - Scheubert, P.*
AU  - Esser, R.*
AU  - Figel, M.
C1  - 57959
C2  - 48258
CY  - The Boulevard, Langford Lane, Kidlington, Oxford Ox5 1gb, England
TI  - A BeOSL finger ring dosemeter.
JO  - Radiat. Meas.
VL  - 131
PB  - Pergamon-elsevier Science Ltd
PY  - 2020
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - To extend the applications of BeOSL technology beyond whole body dosimetry, three new dosemeters were developed: an eye lens dosemeter and a finger ring dosemeter using a single BeOSL detector element and a two-element area dosemeter for work place monitoring. This work describes the new dosemeters, provides data from the radiological characterization of the dosemeters according to IEC 62387 and addresses the issue of measurement uncertainty and detection limits achievable with the BeOSL systems. The response of the new extremity dosemeters in terms of H-p(3) and H-p(0,07) with respect to photon energy and angle of incidence fulfills the IEC 62387 requirements. The area dosemeter fulfills the IEC requirements for workplace monitoring but not the more stringent requirements for environmental dosimetry, due to an under-response for angles of incidence larger than 60 degrees. The results of an uncertainty analysis for the dose evaluation of single element dosemeters show that detection limits in the range of 26 mu Sv-43 mu Sv can be achieved if dedicated background dosemeters are used.
AU  - Hödlmoser, H.
AU  - Greiter, M.
AU  - Bandalo, V.
AU  - Brönner, J.
AU  - Kleinau, P.
AU  - Haninger, T.
AU  - Mende, E.
AU  - Emmerl, M.
AU  - Scheubert, P.*
AU  - Esser, R.*
AU  - Figel, M.
C1  - 58194
C2  - 48191
CY  - The Boulevard, Langford Lane, Kidlington, Oxford Ox5 1gb, England
TI  - Individual monitoring with BeOSL dosemeters: New dosemeters for extremity and area dosimetry.
JO  - Radiat. Meas.
VL  - 132
PB  - Pergamon-elsevier Science Ltd
PY  - 2020
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - The thermoluminescence of different chip cards was measured and analyzed for emergency dosimetry. Three SIM cards that are commonly found in mobile communication providers in South Korea and three smart IC cards that can be purchased online were used for the experiment. Chemical element analysis based on EDS mapping images was carried out and different weight percent of silica was found for each chip card. Glow curves of radiation induced signals through different combinations of optical filters showed blue or red emissions depending on chip cards. Sensitivity change resulting from the thermal stimulation was found to be 1.8 +/- 0.27 and 0.5 +/- 0.06 for the blue and red emission, respectively. In addition, signal fading resulted in more than 20% of the initial signal remaining 20 days after irradiation, when the 100-150 degrees C signal is used. Furthermore, the dose response was recorded from 50 mGy to 10 Gy for each chip card.
AU  - Kim, H.*
AU  - Kim, M.C.*
AU  - Lee, J.*
AU  - Discher, M.*
AU  - Woda, C.
AU  - Lim, S.*
AU  - Chang, I.*
AU  - Lee, S.K.*
AU  - Kim, J.-L.*
AU  - Chung, K.*
C1  - 58942
C2  - 48641
CY  - The Boulevard, Langford Lane, Kidlington, Oxford Ox5 1gb, England
TI  - Characterization of thermoluminescence of chip cards for emergency dosimetry.
JO  - Radiat. Meas.
VL  - 134
PB  - Pergamon-elsevier Science Ltd
PY  - 2020
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - In the framework of the European Project CONFIDENCE ("COping with uNcertainties For Improved modelling and DEcision making in Nuclear emergenCiEs"), the characterization of two applications ("RadioactivityCounter and "GammaPix") that enable dose-rate measurements with an ordinary smartphone was carried out. In case of a nuclear emergency, such softwares allow to use the CMOS sensor of the built-in camera as a radiation detector. This paper presents the results of the scientific investigation on the reliability of the so-called "citizen measurements" performed with 14 different mobile phones chosen among the most common brands sold in 2017. All tests were carried out at room temperature and in different reference fields at the Secondary Standard Dosimetry Laboratory of the Helmholtz Zentrum Munchen. Investigated properties were the response at different dose-rate levels, influence of integration time, background, energy dependence and angular dependence.
AU  - Mafodda, A.
AU  - Woda, C.
C1  - 59820
C2  - 48993
CY  - The Boulevard, Langford Lane, Kidlington, Oxford Ox5 1gb, England
TI  - External dose-rate measurements based on smartphone CMOS sensors.
JO  - Radiat. Meas.
VL  - 137
PB  - Pergamon-elsevier Science Ltd
PY  - 2020
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - With the annual dose limit for the lens of the eye being lowered to 20 mSv from 2019, both new efforts to improve radiation protection for this part of the body and new approved dosemeters for official dose monitoring are required. The individual monitoring services at the Helmholtz Zentrum Miinchen and Dosilab AG, together with MAVIG, have developed a mechanical interface to integrate eye lens dosemeters into radiation protection glasses. MAVIG has designed a new type of radiation protection glasses featuring this dosemeter interface. The two individual monitoring services have independently developed two new types of eye lens dosemeters for the interface. The Munich solution for the eye lens dosemeter is a BeOSL dosemeter for photon radiation with a new detector element introduced by Dosimetrics GmbH in 2018. The Dosilab approach is based on a TLD dosemeter for photon and beta radiation. This work describes the concepts for radiation protection glasses and interface, the new dosemeters, and presents the performance characteristics of the dosemeters in accordance with IEC requirements.
AU  - Hödlmoser, H.
AU  - Greiter, M.
AU  - Bandalo, V.
AU  - Mende, E.
AU  - Brönner, J.
AU  - Kleinau, P.
AU  - Haninger, T.
AU  - Furlan, M.*
AU  - Schmid, M.*
AU  - Esser, R.*
AU  - Scheubert, P.*
AU  - Figel, M.
C1  - 56129
C2  - 46847
CY  - The Boulevard, Langford Lane, Kidlington, Oxford Ox5 1gb, England
SP  - 106-115
TI  - New eye lens dosemeters for integration in radiation protection glasses.
JO  - Radiat. Meas.
VL  - 125
PB  - Pergamon-elsevier Science Ltd
PY  - 2019
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - In this review, the multiscale approach in radiation dosimetry in relation to biological effects is first briefly introduced. The need of dosimetry in microscopic regions, for example in cells, is then addressed, followed by a review of the basic microdosimetric quantities of internal emitters. The requirement of understanding the molecular biological effects of radiation leads to the dosimetric concept in the nanometer ranges, where the initial events produced at the molecular level cause the subsequent cellular and tissue effects that may lead to cancer. Track structure theory is particularly introduced in nanodosimetry for internal emitters. The relationship between the quantities in macroscopic dosimetry, e.g. absorbed dose, the microdosimetric quantities, e.g. specific energy and lineal energy, and the nanodosimetric characteristics, the track structures is inherently established in a derivational way. The significance of microdosimetric and nanodosimetric quantities in understanding and interpreting the mechanisms of radiobiological effects is addressed. Several applications of microdosimetry and nanodosimetry for internal emitters in radon and thoron progeny dosimetry and risk analysis, in targeted radionuclide therapy, in modelling of DNA damages and as a tool in the potential interpretation of dose-response relationship at low doses and dose rates are given. Finally, the potential future development of internal microdosimetry and nanodosimetry is outlined.
AU  - Li, W.
AU  - Hofmann, W.*
AU  - Friedland, W.
C1  - 53662
C2  - 44786
SP  - 29-42
TI  - Microdosimetry and nanodosimetry for internal emitters.
JO  - Radiat. Meas.
VL  - 115
PY  - 2018
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - In neutron fields including neutron energies above 20 MeV a conventional neutron dosimeter is not suitable for measurements of neutron personal dose equivalent, Hp(10), over the whole energy range. Therefore, for such fields an electronic neutron dosimeter has been developed recently at Helmholtz Zentrum München (HMGU). In general, neutron dose measurements performed with this dosimeter at neutron energies below 2 MeV show an accuracy of about 30% [1]. Here we report the use of this dosimeter at the CERN-EU high-energy Reference Field (CERF) facility in Geneva, Switzerland. At this facility the available neutron fields include neutrons with energies below, but also above 20 MeV. In the present paper, personal dose equivalent (Hp(10)) values obtained with the ELectronic neutron DOsimeter (ELDO) are compared to neutron personal dose equivalent (Hp(10)) values obtained with the HMGU extended-range Bonner Sphere Spectrometer, and to reference values from FLUKA Monte Carlo simulations provided by CERF. It is shown that for continuous neutron spectra as those at CERF behind concrete shielding or secondary neutrons from cosmic rays, the dosimeter results are satisfactory for radiation protection purposes. However, in neutron fields including neutrons above about 7 MeV, where the major neutron dose contribution is from neutrons between 10 keV and several MeV (like those at CERF behind iron shielding), the doses provided by ELDO might be too small and care must be taken in interpreting the results.
AU  - Wielunski, M.
AU  - Brall, T.
AU  - Dommert, M.*
AU  - Trinkl, S.*
AU  - Rühm, W.
AU  - Mares, V.
C1  - 53623
C2  - 44757
SP  - 12-18
TI  - Electronic neutron dosimeter in high-energy neutron fields.
JO  - Radiat. Meas.
VL  - 114
PY  - 2018
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Silicates extracted from tobacco dust in cigarettes were investigated for their suitability as an emergency dosimeter in accidental situation using thermoluminescence technique. A typical glow curve (at a heating rate of 2 degrees C s(-1)) of irradiated dust silicates in the transmission window between 300 and 500 nm has two prominent peaks at about 83 degrees C and 137 degrees C and a weak one at about 181 degrees C which were all distinguishable from the natural thermoluminescence. The TL spectrum of highly irradiated dust samples showed the existence of three dominant emissions at 1.66 eV (745 nm), 2.2 eV (560 nm) and 2.81 eV (440 nm), which are similar to those reported for feldspar. Repeated irradiation and TL measurement did not affect the sensitivity of the 137 degrees C peak, if the glow curve is terminated at 300 degrees C. A linear dose response of the TL signal was observed for doses between 0.1 and 10 Gy. A preheat temperature of 110 degrees C was found to be optimal for the emptying of the low temperature peak which is not stable. The TL signal is not stable but fades with time since irradiation. Furthermore it can be bleached by daylight but the dust seemed to be sufficiently light shielded in intact cigarettes. Based on the experimental dosimetric properties, a measurement protocol for the detection of absorbed radiation dose was developed. The result of a dose recovery test showed a reasonable agreement between fading corrected dose and given dose. (c) 2017 Elsevier Ltd. All rights reserved.
AU  - Ademola, J.A.
AU  - Woda, C.
AU  - Bortolin, E.*
C1  - 50480
C2  - 42447
CY  - Oxford
SP  - 443-449
TI  - Thermoluminescence investigations on tobacco dust as an emergency dosimeter.
JO  - Radiat. Meas.
VL  - 106
PB  - Pergamon-elsevier Science Ltd
PY  - 2017
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - The dosimetric properties of resistor substrates extracted from the circuit board of mobile phones were studied in detail using Thermoluminescence for the purpose of dose reconstruction following a radiological accident or attack. Many studies have shown the usefulness of this material using Optically Stimulated Luminescence but TL studies are scarce. The typical glow curve of a set of irradiated resistors has a peak at about 170 °C. Unexposed resistors showed a strong zero dose signal in the higher temperature region, peaking between 300 and 350 °C, which also led to a minor zero dose being detected in the chosen integration window of 100-200 °C. Exposure to white light can significantly increase the zero dose, presumably due to phototransfer of charge carriers from deep traps into the dosimetric trap. The dose response of the TL signal was linear up to several Gy but an irreversible sensitivity change was observed in the first thermal readout. A correction factor was therefore deduced from a number of dose recovery tests. Similar to the OSL signal, the TL signal is not stable but fades with time since irradiation. Overall, a slightly smaller fading rate up to 60 days was observed for the TL signal, as compared to the OSL signal. A protocol is proposed for TL based on the measured properties and validated in irradiation trials.
AU  - Ademola, J.A.
AU  - Woda, C.
C1  - 51636
C2  - 43405
CY  - Oxford
SP  - 13-21
TI  - Thermoluminescence of electronic components from mobile phones for determination of accident doses.
JO  - Radiat. Meas.
VL  - 104
PB  - Pergamon-elsevier Science Ltd
PY  - 2017
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Under the umbrella of the European Radiation Dosimetry Group (EURADOS), different working groups have responded to the requests of monitoring services in Europe for independent tests of dosimetry systems for harmonization and quality assurance. After having performed regular intercomparisons of personal dosemeters, EURADOS Working Group 3, "Environmental Dosimetry", performed the first EURADOS intercomparison for passive ambient dose equivalent, abbreviated H*(10), area dosemeters used for environmental monitoring in 2014 (IC2014env). Such dosimetry systems are generally used to monitor nuclear installations, besides other applications. The results of this intercomparison with a total of more than 500 dosemeters help to better understand influence parameters and the possible accuracy of typical dosimetric measurements using passive dosemeters. (C) 2017 Elsevier Ltd. All rights reserved.
AU  - Dombrowski, H.*
AU  - Duch, M.A.*
AU  - Hranitzky, C.*
AU  - Kleinau, P.
AU  - Neumaier, S.*
AU  - Ranogajec-Komor, M.*
AU  - Rodriguez, R.L.*
C1  - 51363
C2  - 43040
CY  - Oxford
SP  - 229-234
TI  - EURADOS intercomparison of passive H*(10) area dosemeters 2014.
JO  - Radiat. Meas.
VL  - 106
PB  - Pergamon-elsevier Science Ltd
PY  - 2017
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - EURADOS Working Group 3 (WG3) aims at providing information about the correct measurement of the ambient dose equivalent (rate) in the environment and has a specific subgroup (WG3-SG2) that focuses on passive environmental dosimetry. One of the initial tasks of the subgroup was to gain an overview of passive dosimetry practices in Europe. On the basis of a survey carried out by this subgroup in 2013/2014, information on the state-of-the-art was gained, several conclusions were drawn and some open questions have been identified, e.g. the harmonization in the terminology, uncertainty assessment procedures and corrections of measured values by passive dosemeters due to transport and climate. (C) 2017 Elsevier Ltd. All rights reserved.
AU  - Duch, M.A.*
AU  - Dombrowski, H.*
AU  - Hranitzky, C.*
AU  - Kleinau, P.
AU  - Neumaier, S.*
AU  - Ranogajec-Komor, M.*
AU  - Rodriguez, R.L.*
C1  - 50845
C2  - 42917
CY  - Oxford
SP  - 242-245
TI  - Status of passive environmental dosimetry in Europe.
JO  - Radiat. Meas.
VL  - 106
PB  - Pergamon-elsevier Science Ltd
PY  - 2017
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - In 2008 EURADOS (the European Radiation Dosimetry Group) started a programme of regular dosemeter intercomparisons to assist harmonisation of individual monitoring services (IMS). In 2015, IC2015(ext) for extremity dosemeters was coordinated by the Seibersdorf Labor GmbH/Austria. In total 72 different systems were tested. These were from 52 IMS from 21 countries and one international institution. Extremity dosemeters (ring, wrist/ankle and fingertip) were irradiated, dose quantity H-p(0.07), with photon and beta radiations. Irradiations were carried out by the accredited calibration laboratory VSL (Dutch national metrology institute/Delft). The irradiation plan was designed to allow the systems to be tested for linearity, energy response and angular response. The results show that, in general, extremity dose meters perform better for photon than for beta radiations. 57% of systems showed at least one outlier, as defined in ISO-14146, revealing that there is still scope for improvement in the field of extremity dosimetry. This paper presents the results of IC2015(ext) and compares these results with IC2009(ext).
AU  - Stadtmann, H.*
AU  - McWhan, A.F.*
AU  - Figel, M.
AU  - Grimbergen, T.W.M.*
AU  - Romero, A.M.*
AU  - Gaertner, C.*
C1  - 52793
C2  - 44214
CY  - Oxford
SP  - 285-289
TI  - EURADOS intercomparisons for individual monitoring services: Results of the 2015 extremity dosemeter intercomparison for photon and beta radiations.
JO  - Radiat. Meas.
VL  - 106
PB  - Pergamon-elsevier Science Ltd
PY  - 2017
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Recently, two independent electronic dosimeters for individual monitoring have been developed at the Helmholtz Center Munich, Germany, one for photons and one for neutrons. Calibration of these dosimeters was performed using mono-energetic neutrons (energy range: 144 keV–14.8 MeV) and photons (12 keV–1.3 MeV), and the resulting calibration curves were compared to Monte Carlo simulations using the GEANT4 tool kit. In the present paper, an integrated dosimeter prototype is described which combines both dosimeters and therefore allows measurement of total dose in mixed neutron/photon radiation fields. It is demonstrated that the neutron channel of the combined dosimeter is insensitive to photons, while the photon channel is insensitive to neutrons. The prototype was tested in the field of an Am-Be neutron source which also includes a photon component. When the Am-Be neutron source was shielded by 9 mm lead, the combined dosimeter indicated a dose rate of 122.6 ± 1.0 μSv/h from neutrons and 7.3 ± 0.1 μSv/h from photons. In contrast, when the Am-Be neutron source was not shielded by lead, the combined dosimeter indicated a dose rate of 125.8 ± 1.0 μSv/h from neutrons and 65.9 ± 0.1 μSv/h from photons indicating a significant contribution from photons to total dose. In a second experiment when the Am-Be neutron source was closer to the combined dosimeter and a 137Cs source was added, a neutron dose rate of 421 ± 20 μSv/h and a photon dose rate of 849 ± 6 μSv/h was obtained. It is concluded that this instrument can be used in mixed photon-neutron fields with doses and dose rates typical for radiation protection purposes.
AU  - Wielunski, M.
AU  - Trinkl, S.
AU  - de Souza-Santos, D.*
AU  - Wahl, W.*
AU  - Rühm, W.
C1  - 51117
C2  - 42659
CY  - Oxford
SP  - 13-21
TI  - The HMGU combined neutron and photon dosemeter.
JO  - Radiat. Meas.
VL  - 101
PB  - Pergamon-elsevier Science Ltd
PY  - 2017
SN  - 1350-4487
ER  - 

TY  - JOUR
AU  - Woda, C.
AU  - Figel, M.
AU  - Regulla, D.F.
C1  - 52503
C2  - 44016
CY  - Oxford
SP  - 1-2
TI  - Editorial: The 18th International Conference on Solid State Dosimetry (SSD18).
JO  - Radiat. Meas.
VL  - 106
PB  - Pergamon-elsevier Science Ltd
PY  - 2017
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Touchscreen glasses of mobile phones are sensitive to ionizing radiation and have the potential of usage as an emergency dosimeter for retrospective dosimetry for the purpose of triage after a radiological accident or attack. In this study the TL glow curves and dosimetric properties of touchscreen glasses were studied in detail, such as intrinsic background dose, dose response, reproducibility, optical stability and long-term stability of the TL signal.Preliminary results are additionally presented to minimize the intrinsic background dose by mechanically removing the surface layer of the glass samples. Additionally chemical element analyses of the touchscreen glass samples were carried out to investigate the difference between glass samples which show a TL signal and samples which show neither an intrinsic zero dose signal nor a radiation induced TL signal.An irradiation trial using glass samples stored in the dark demonstrated a successful dose recovery. However, when applying a realistic, external light exposure scenario, dose underestimation was observed, even though samples were pre-bleached prior to measurement. More investigations have to be carried out in the future to solve the challenge of the low optical stability of the TL signal, if touchscreen glasses are to be used as a reliable emergency dosimeter.
AU  - Discher, M.
AU  - Bortolin, E.*
AU  - Woda, C.
C1  - 48415
C2  - 41060
CY  - Oxford
SP  - 44-51
TI  - Investigations of touchscreen glasses from mobile phones for retrospective and accident dosimetry.
JO  - Radiat. Meas.
VL  - 89
PB  - Pergamon-elsevier Science Ltd
PY  - 2016
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - This paper reports the near space ballooning experiment carried out at Australian outback town West Wyalong (33°51′S, 147°24′E) on 19 July 2015. Several dedicated electronic detectors including digital temperature and acceleration (vibration) sensors and an energy compensated PIN-diode gamma ray dosimeter were installed in a thermally insulated Styrofoam payload box. A 9 V Lithium-Polymer battery powered all the devices. The payload box was attached to a helium-filled latex weather balloon and set afloat. The balloon reached a peak burst altitude of 30 km and then soft-landed aided by a self-deploying parachute 66.2 km away form the launch site. The payload box was retrieved and data collected from the electronic sensors analysed. The integrated cosmic ray induced photon ambient dose equivalent recorded by the PIN diode detector was evaluated to be 0.36 ± 0.05 μSv. Furthermore, a high-altitude extended version of commercially available aviation dosimetry package EPCARD.Net (European Program package for the Calculation of Aviation Route Doses) was used to calculate the ambient dose equivalents during the balloon flight. The radiation environment originated from the secondary cosmic ray shower is composed of neutrons, protons, electrons, muons, pions and photons. The photon ambient dose equivalent estimated by the EPCARD.Net code found to be 0.47 ± 0.09 μSv. The important aspects of balloon based near-space radiation dosimetry are highlighted in this paper.
AU  - Mukherjee, B.*
AU  - Wu, X.*
AU  - Maczka, T.
AU  - Kwan, T.*
AU  - Huang, Y.*
AU  - Mares, V.
C1  - 49584
C2  - 40842
CY  - Oxford
SP  - 65-72
TI  - Near space radiation dosimetry in Australian outback using a balloon borne energy compensated PIN diode detector.
JO  - Radiat. Meas.
VL  - 94
PB  - Pergamon-elsevier Science Ltd
PY  - 2016
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - A powder sandwich technique was applied to determine thoron (220Rn) and radon (222Rn) emanation rates for a granular material. The feature of this technique is the sample preparation, in which a granular material is put and fixed between two membrane filters. Airflow is directly given to this sandwich sample, will include thoron and radon emanated from the material, and then is transferred to the detector. This method makes sure that thoron and radon emanated are not retained in pore space within the sample volume, which is crucial for the appropriate emanation test. This technique was first introduced by Kanse etal. (2013) with the intention to measure the emanation of thoron - but not of radon - from materials having much higher 224Ra activity than 226Ra. In the present study, the methodology for the discriminative determination of thoron and radon emanation rates from a granular material has been examined using a flow-through scintillation cell and sandwich sample. The mathematical model was developed to differentiate total alpha counts into thoron- and radon-associated counts. With a sample of uranium ore, this model was experimentally validated by comparison between the scintillation cell and a reference detector that can discriminatively measure thoron and radon concentrations. Furthermore, the detection limits and uncertainties were evaluated to discuss the characteristics of this method. Key parameters for improving the determination of thoron and radon emanations were found to be the background radon concentration and the leakage of radon from the measurement system, respectively. It was concluded that the present method is advantageous to a sample that has much higher 226Ra activity than 224Ra.
AU  - Sakoda, A.
AU  - Meisenberg, O.
AU  - Tschiersch, J.
C1  - 47919
C2  - 39746
CY  - Oxford
SP  - 8-13
TI  - An approach to discriminatively determine thoron and radon emanation rates for a granular material with a scintillation cell.
JO  - Radiat. Meas.
VL  - 89
PB  - Pergamon-elsevier Science Ltd
PY  - 2016
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - It has been demonstrated that glass display of mobile phones can be used as a device for accident dosimetry. Published studies concentrated on the experimental investigation of parts of the glass display. In the work presented here, the experimental results are compared with results of radiation transport calculations using the Monte Carlo code MCNP5. An experimental setup of an irradiation of an extracted glass display is simulated. The simulation is then extended to a simulation of a modern day mobile phone consisting of all major parts. Simulations are performed for various irradiation conditions and different geometric and material properties. The results of the simulation show a good agreement with the experiments for an extracted glass sample as well as for an actual modern mobile phone. The glass display is exposed to radiation in various angular and energy distributions. Simulated results were compared to experimentally determined results. The effects of the irradiation condition on the photon energy dependence were investigated and variations in the material constants of the display glass composition were discussed. This work affirms the usability of a mobile phone as a versatile and flexible accident radiation detector.
AU  - Discher, M.
AU  - Hiller, M.
AU  - Woda, C.
C1  - 43868
C2  - 36754
CY  - Oxford
SP  - 21-28
TI  - MCNP simulations of a glass display used in a mobile phone as an accident dosimeter.
JO  - Radiat. Meas.
VL  - 75
PB  - Pergamon-elsevier Science Ltd
PY  - 2015
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Determining the activity size distribution of radioactive aerosol particles requires sophisticated and heavy equipment, which makes measurements at large number of sites difficult and expensive. Therefore three methods for a retrospective determination of size distributions from aerosol filter samples in the laboratory were tested for their applicability. Extraction into a carrier liquid with subsequent nebulisation showed size distributions with a slight but correctable bias towards larger diameters compared with the original size distribution. Yields in the order of magnitude of 1% could be achieved. Sonication-assisted extraction into a carrier liquid caused a coagulation mode to appear in the size distribution. Sonication-assisted extraction into the air did not show acceptable results due to small yields. The method of extraction into a carrier liquid without sonication was applied to aerosol samples from Chernobyl in order to calculate inhalation dose coefficients for 137Cs based on the individual size distribution. The effective dose coefficient is about half of that calculated with a default reference size distribution.
AU  - Meisenberg, O.
AU  - Tschiersch, J.
C1  - 44426
C2  - 36918
CY  - Oxford
SP  - 29-35
TI  - Test of methods for retrospective activity size distribution determination from filter samples.
JO  - Radiat. Meas.
VL  - 76
PB  - Pergamon-elsevier Science Ltd
PY  - 2015
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - In 2011 a measurement intercomparison was launched by EURADOS WG7, with the objective of providing the participants with the tools to calibrate their detection systems for detection of 241Am in the skull bone, and evaluate the variability due to the used of the different calibration phantoms. Three skull phantoms were used in this intercomparison: the USTUR Case 0102 skull phantom, the BfS skull phantom and the CSR skull phantom. Very good agreement was found between the results of the twelve participating laboratories, with relative deviations of less than 15% for the BfS phantom and less than 17% for the USTUR phantom when measurement efficiency in defined positions was compared. However, the phantoms' measured absolute 241Am activities showed discrepancies of up to a factor of 3.4. This is mainly due to the physical differences between the standard calibration phantoms used by the participants and those used in this intercomparison exercise.
AU  - Nogueira, P.
AU  - Rühm, W.
AU  - Lopez, M.A.*
AU  - Vrba, T.*
AU  - Buchholz, W.*
AU  - Fojtik, P.*
AU  - Etherington, G.*
AU  - Broggio, D.*
AU  - Huikari, J.*
AU  - Marzocchi, O.*
AU  - Lynch, T.*
AU  - Lebacq, A.L.*
AU  - Li, C.*
AU  - Os̈ko, J.*
AU  - Malatova, I.*
AU  - Franck, D.*
AU  - Breustedt, B.*
AU  - Leone, D.*
AU  - Scott, J.*
AU  - Shutt, A.L.*
AU  - Hauck, B.*
AU  - Capello, K.*
AU  - Pérez-López, B.*
AU  - Navarro-Amaro, J.F.*
AU  - Pliszczyński, T.*
AU  - Fantínová, K.*
AU  - Tolmachev, S.Y.*
C1  - 46799
C2  - 37848
SP  - 64-73
TI  - EURADOS 241Am skull measurement intercomparison.
JO  - Radiat. Meas.
VL  - 82
PY  - 2015
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - When a scintillation cell is used for radon measurement, detection efficiencies for individual alpha emitters (222Rn, 218Po and 214Po) are required depending on the methods of data analysis. To estimate their detection efficiencies, Monte Carlo simulation has been implemented to track alpha particles emitted in the cell in the static condition. However, such an effort has not been made for the flow-through condition. The present study describes an attempt to obtain an empirical parameter which is necessary to predict the behavior of radon progeny in the flow-through cell: the fraction of the progeny generated in the cell which is deposited onto the wall. As a result, it was found that the deposition fraction of 218Po decreases exponentially with increasing flow rate in the range of 0.25–2 l min−1. An empirical formula was acquired to estimate the deposition fraction of 218Po as a function of flow rate. This result is helpful in understanding the characteristics of the scintillation cell. The empirical formula derived in this study can also be applied to predicting the behavior of thoron progeny (212Pb and its progeny) in continuous thoron measurements with the flow-through scintillation cell.
AU  - Sakoda, A.
AU  - Meisenberg, O.
AU  - Tschiersch, J.
C1  - 44850
C2  - 37023
CY  - Oxford
SP  - 41-45
TI  - Behavior of radon progeny produced in a scintillation cell in the flow-through condition.
JO  - Radiat. Meas.
VL  - 77
PB  - Pergamon-elsevier Science Ltd
PY  - 2015
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - In the framework of the EU-FP7 MULTIBIODOSE project, two protocols using OSL of resistors removed from the circuit board of mobile phones were developed with the aim to use the resistors as fortuitous dosimeters in the event of a large scale radiological accident. This paper presents the results of an inter-laboratory comparison carried out under the umbrella of EURADOS. The two aims of this exercise were the validation of the MULTIBIODOSE protocols by a large number of laboratories and the dissemination of the method with the objective of preparing the basis for a network that could increase Europe's response capacity in the case of a mass casualty radiological emergency. Twelve institutes from eleven European countries and one institute from the USA, with various degrees of expertise in OSL dosimetry, took part in the OSL inter-laboratory comparison. Generally, a good agreement within uncertainties was observed between estimated and nominal doses.
AU  - Bassinet, C.*
AU  - Woda, C.
AU  - Bortolin, E.*
AU  - Della Monaca, S.*
AU  - Fattibene, P.*
AU  - Quattrini, M.C.*
AU  - Bulanek, B.*
AU  - Ekendahl, D.*
AU  - Burbidge, C.I.*
AU  - Cauwels, V.*
AU  - Kouroukla, E.C.*
AU  - Geber-Bergstrand, T.*
AU  - Mrozik, A.*
AU  - Marczewska, B.*
AU  - Bilski, P.X.*
AU  - Sholom, S.V.*
AU  - McKeever, S.W.S.*
AU  - Smith, R.W.*
AU  - Veronese, I.*
AU  - Galli, A.*
AU  - Panzeri, L.*
AU  - Martini, M.*
C1  - 31221
C2  - 34211
CY  - Oxford
SP  - 475-479
TI  - Retrospective radiation dosimetry using OSL of electronic components: Results of an inter-laboratory comparison.
JO  - Radiat. Meas.
VL  - 71
PB  - Pergamon-elsevier Science Ltd
PY  - 2014
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Previous studies have shown that glass displays extracted from mobile phones are suitable as emergency dosimeters in case of an accidental radiation overexposure using the thermoluminescence (TL) method. So far these studies have focused only on recovering the absorbed dose to the material. However, dose in air or dose to the victim carrying the device might be significantly different. Therefore the aim of this work was to investigate photon energy dependence and angular response of glass display used in modern mobile phones. An over-response of about a factor of five is observed for low photon energies compared to the response to Cs-137 (662 keV) which is in reasonable agreement with calculated values mass energy-absorption coefficients of glass and air. Little variation in the energy dependence can be seen for glass displays coming from three different mobile phone models. The angular response for display glass is flat with regard to air kerma within the incident angle of ±60°, independent of the irradiation setup used (with a water phantom or with air kerma reference conditions). For incident angles of 90° the shielding effect of the mobile phones becomes important. With the dosimetric characterization of the photon energy and angular dependencies the absorbed dose in a glass display can be transferred to a reference air kerma dose and provides a useful option for retrospective accident dosimetry.
AU  - Discher, M.
AU  - Greiter, M.
AU  - Woda, C.
C1  - 31433
C2  - 34542
CY  - Oxford
SP  - 471-474
TI  - Photon energy dependence and angular response of glass display used in mobile phones for accident dosimetry.
JO  - Radiat. Meas.
VL  - 71
PB  - Pergamon-elsevier Science Ltd
PY  - 2014
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Glass displays of mobile phones are sensitive to ionizing radiation and can be used for retrospective dosimetry for the purpose of triage after a radiological accident or attack. In this study the two main types of glass display that are used in modern mobile phones were investigated using thermoluminescence (TL) emission spectrometry. A different TL spectrum was observed for the glass display of category A (lime-aluminosilicate glass) and category B (boron-silicate glass). Based on the spectral measurements an optimized detection window was chosen to re-evaluate the dosimetric properties (dose response, optical and long-term stability) of glass display category B.
AU  - Discher, M.
AU  - Woda, C.
C1  - 31627
C2  - 34668
CY  - Oxford
SP  - 480-484
TI  - Thermoluminescence emission spectrometry of glass display in mobile phones and resulting evaluation of the dosimetric properties of a specific type of display glass.
JO  - Radiat. Meas.
VL  - 71
PB  - Pergamon-elsevier Science Ltd
PY  - 2014
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Electron Paramagnetic Resonance (EPR) spectroscopy with tooth enamel is a widely used method of dosimetry. The accuracy of EPR tooth dosimetry depends on the spectrum processing procedure, the quality of which, in its turn, relies on instrumental noise and the signals from impurities. This is especially important in low-dose evaluation. The current paper suggests a method to estimate the accuracy of a specific spectrum processing procedure. The method is based on reconstruction of the radiation-induced signal (RIS) from a simulated spectrum with known RIS intensity. The Monte Carlo method was used for the simulations. The model of impurity and noise signals represents a composite residual spectrum (CRS) obtained by subtraction of the reconstructed MS and the native background signal (BGS) from enamel spectra measured in HMGU (Neuherberg, Germany) and IMP (Yekaterinburg, Russia). The simulated spectra were deconvoluted using a standard procedure. The method provides an opportunity to compare the simulated "true" RIS with reconstructed values. Two modifications of the EPR method were considered: namely, with and without the use of the reference Mn2+ signals. It was observed that the spectrum processing procedure induces a nonlinear dose response of the reconstructed EPR amplitude when the height of the true MS is comparable with the amplitudes of noise-like random splashes of CRS. The area of nonlinearity is below the limit of detection (DL). The use of reference Mn2+ signals can reduce the range of nonlinearity. However, the impact of the intensities of CRS random signals on nonlinearity is two times higher than the one observed when the reference signals were not used. The reproducibility of the software response is also dependent on both the amplitude of the CRS and the use of a reference signal, and it is also two times more sensitive to the amplitude of the CRS. In most EPR studies, all of the data are used, even those for which the dose value is lower than the DL This study shows that low doses evaluated with the help of linear dose-response can be significantly overestimated. It is recommended that linear dose response calibration curves be constructed using only data above the DL. Data below the DL should be interpreted cautiously.
AU  - Ivanov, D.V.*
AU  - Wieser, A.
AU  - Shishkina, E.A.*
AU  - Ustinov, V.V.*
C1  - 32444
C2  - 35053
SP  - 7-13
TI  - Effect of spectrum processing procedure on the linearity of EPR dose reconstruction in tooth enamel.
JO  - Radiat. Meas.
VL  - 68
PY  - 2014
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Bonner Spheres Spectrometry in its high-energy extended version is an established method to quantify neutrons at a wide energy range from several meV up to more than 1 GeV. In order to allow for quantitative measurements, the responses of the various spheres used in a Bonner Sphere Spectrometer (BSS) are usually simulated by Monte Carlo (MC) codes over the neutron energy range of interest. Because above 20 MeV experimental cross section data are scarce, intra-nuclear cascade (INC) and evaporation models are applied in these MC codes. It was suspected that this lack of data above 20 MeV may translate to differences in simulated BSS response functions depending on the MC code and nuclear models used, which in turn may add to the uncertainty involved in Bonner Sphere Spectrometry, in particular for neutron energies above 20 MeV. In order to investigate this issue in a systematic way, EURADOS (European Radiation Dosimetry Group) initiated an exercise where six groups having experience in neutron transport calculations with the MC codes (MCNP, MCNPX, FLUKA, PHITS, MARS, or GEANT4) calculated the responses of a bare He-3 proportional counter, a He-3 proportional counter embedded in the middle of a 9 inch polyethylene sphere, and a He-3 proportional counter centred in a 9 inch polyethylene sphere containing a lead shell, at neutron energies of 1, 10, 100, and 1000 MeV. In general, calculated responses agreed very well for neutron energies below 20 MeV, whatever MC code used. At higher energies, however, certain differences were observed among the different calculations, which may mainly be attributed to the application of different INC models and their parameters. It was found that up to 1 GeV most of the results ranged between calculations previously published that were obtained with MCNP/LAHET using the Bertini INC model and GEANT4 using the Binary and Bertini INC models. These results indicate that use of different MC codes and INC models for the calculation of BSS response functions may result in an uncertainty of unfolded neutron fluences above 20 MeV of about 20%.
AU  - Rühm, W.
AU  - Mares, V.
AU  - Pioch, C.
AU  - Agosteo, S.*
AU  - Endo, A.*
AU  - Ferrarini, M.*
AU  - Rakhno, I.*
AU  - Rollet, S.*
AU  - Satoh, D.*
AU  - Vincke, H.*
C1  - 32269
C2  - 35003
CY  - Oxford
SP  - 24-34
TI  - Comparison of Bonner sphere responses calculated by different Monte Carlo codes at energies between 1 MeV and 1 GeV - potential impact on neutron dosimetry at energies higher than 20 MeV.
JO  - Radiat. Meas.
VL  - 67
PB  - Pergamon-elsevier Science Ltd
PY  - 2014
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - In 2008, EURADOS (the European Radiation Dosimetry Group) started to organise a self-sustained programme of regular intercomparisons with the aims of encouraging and facilitating the participation of individual monitoring services (IMS) in intercomparisons. To date, three intercomparisons for whole body dosemeters (IC2008, IC2010 and IC2012) and one for extremity dosemeters (IC2009) have been carried out. This paper presents the recent results of the 2012 intercomparison for whole body dosemeters. At the 2012 intercomparisons 75 institutes with 87 dosimetry systems (most passive) participated from 28 European and 2 non-European countries. For the irradiations a number of different reference photon radiation qualities (x-ray and nuclide sources) were used. The results show that 90% of all systems fulfil the general performance criteria from ISO 14146. The paper gives a comprehensive overview on the performance of various European dosimetry services and the influence of the dosemeter type and detector material on the resulting response values.
AU  - Stadtmann, H.*
AU  - McWhan, A.F.*
AU  - Figel, M.
AU  - Dobriynska, W.*
AU  - Grimbergen, T.W.M.*
AU  - Romero, A.M.*
C1  - 43241
C2  - 36290
CY  - Oxford
SP  - 416-420
TI  - EURADOS intercomparisons for individual monitoring services: Results of the 2012 whole body intercomparison.
JO  - Radiat. Meas.
VL  - 71
PB  - Pergamon-elsevier Science Ltd
PY  - 2014
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - This paper deals with the thermoluminescence (TL) study of glass displays from mobile phones with the aim to use them as emergency dosimeters after an accident involving ionizing radiation. Dosimetric properties are analysed in order to examine and to critically evaluate the usability. Tests are carried out regarding the characterization of the radiation induced TL signal and the zero dose signal (intrinsic background) on a variety of display samples. Investigations on the thermal and optical stability of TL signals are carried out. The detection limit is mainly determined by the variability of the zero dose signal and lies in the range of 300-400 mGy. A linear relationship between the measured TL signal and the applied dose is observed for doses between 10 mGy and 20 Gy. A measurement protocol for the detection of absorbed radiation dose is developed, considering the experimental dosimetric properties. A reconstruction of the absorbed dose is possible using glass samples from mobile phones, if the signal loss due to storage and optical bleaching of the TL signal is adequately corrected for. This was confirmed by realistic tests. (c) 2013 Elsevier Ltd. All rights reserved.
AU  - Discher, M.
AU  - Woda, C.
C1  - 25976
C2  - 32035
SP  - 12-21
TI  - Thermoluminescence of glass display from mobile phones for retrospective and accident dosimetry.
JO  - Radiat. Meas.
VL  - 53-54
PB  - Pergamon-Elsevier Science
PY  - 2013
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Previous studies have demonstrated that mobile phones can be used as suitable emergency dosimeters in case of an accidental radiation overexposure. Glass samples extracted from displays of mobile phones are sensitive to ionizing radiation and can be measured using the thermoluminescence (TL) method. A non-radiation induced background signal (so-called zero dose signal) was observed which overlaps with the radiation induced signal and consequently limits the minimum detectable dose. Investigations of several glasses from different displays showed that it is possible to reduce the zero dose signal up to 90% by etching the glass surface with concentrated hydrofluoric acid. With this approach a reduction of the detection limit of a factor of four, corresponding to approximately 80 mGy, was achieved. Dosimetric properties of etched samples are presented and developed protocols validated by dose recovery tests under realistic conditions. With the improvements in sample preparation the proposed method of dose determination is a competitive alternative to OSL/TL measurements of electronic components and chip cards and provides a useful option for retrospective accident dosimetry.
AU  - Discher, M.
AU  - Woda, C.
AU  - Fiedler, I.
C1  - 26124
C2  - 32081
SP  - 240-243
TI  - Improvement of dose determination using glass display of mobile phones for accident dosimetry.
JO  - Radiat. Meas.
VL  - 56
PB  - Pergamon-Elsevier
PY  - 2013
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - At the accredited PSI Calibration Laboratory neutron reference fields traceable to the national standards of the Physikalisch-Technische Bundesanstalt (PTB) in Germany are available for the calibration of ambient and personal dose equivalent (rate) meters and passive dosimeters. The photon contribution to the ambient dose equivalent in the neutron fields of the Cf-252 and Am-241-Be sources was measured using various photon dose rate meters and active and passive dosimeters. Measuring photons from a neutron source usually involves considerable uncertainties due to the presence of neutron induced photons in the room, due to a non-zero neutron sensitivity of the photon detector, and last but not least due to the energy response of the photon detectors. Therefore eight independent detectors and methods were used to obtain a reliable estimate for the photon contribution of the two sources as an average of the individual methods. For the Am-241-Be source a photon contribution of approximately 4.9% was determined and for the Cf-252 source a contribution of 3.6%.
AU  - Hödlmoser, H.*
AU  - Boschung, M.*
AU  - Meier, K.*
AU  - Stadtmann, H.*
AU  - Hranitzky, C.*
AU  - Figel, M.
AU  - Mayer, S.*
C1  - 10830
C2  - 30379
SP  - 567-570
TI  - Photon contributions from the 252Cf and 241Am-Be neutron sources at the PSI Calibration Laboratory.
JO  - Radiat. Meas.
VL  - 47
IS  - 8
PB  - Elsevier
PY  - 2012
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - A conceptual design is presented to use measurements of localized absorbed dose in inner cities for production of high resolution maps of the radioactive contamination following a nuclear emergency or radiological attack. The doses are derived from luminescent detectors pre-fixed at places of high importance (e.g. public squares). For such an environmental dosimeter, BeO is used, which can be read out using optically stimulated luminescence (OSL). A suitable casing of black Perspex has been developed to give a sufficiently accurate estimate of the air kerma value at the detector position. The dosimeter is characterized according to light tightness, dose response and angular photon energy dependence. A short overview of the approach for map production is also given.
AU  - Woda, C.
AU  - Kaiser, J.C.
AU  - Urso, L.
AU  - Greiter, M.
C1  - 10692
C2  - 30355
SP  - 609-613
TI  - An environmental BeO-OSL dosimeter for emergency response.
JO  - Radiat. Meas.
VL  - 47
IS  - 8
PB  - Elsevier
PY  - 2012
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - The potential of optically stimulated luminescence of wire-bond chip card modules with molded encapsulations for retrospective and accident dosimetry is investigated. Contact-based and contactless modules were studied, the latter finding potential use in electronic documents (e.g. electronic passports, electronic identity cards). Investigations were carried out on intact as well as chemically prepared modules, extracting the filler material. Contact-based modules are characterized according to zero dose signal, correlation between OSL and TL, dose response and long-term signal stability. For prepared modules, the minimum detectable dose immediately after irradiation is 3 mGy and between 20 and 200 mGy for contact-based and contactless modules, respectively. Dose recovery tests on contact-based modules indicate that the developed methodology yields results with sufficient accuracy for measurements promptly after irradiation, whereas a systematic underestimation is observed for longer delay times. The reasons for this behaviour are as yet not fully understood.
AU  - Woda, C.
AU  - Fiedler, I.
AU  - Spöttl, T.*
C1  - 10838
C2  - 30399
SP  - 1068-1073
TI  - On the use of OSL of chip card modules with molding for retrospective and accident dosimetry.
JO  - Radiat. Meas.
VL  - 47
IS  - 11
PB  - Elsevier
PY  - 2012
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - This paper presents the results of the 4th International Comparison of in vitro electron paramagnetic resonance dosimetry with tooth enamel, where the performance parameters of tooth enamel dosimetry methods were compared among sixteen laboratories from all over the world. The participating laboratories were asked to determine a calibration curve with a set of tooth enamel powder samples provided by the organizers. Nine molar teeth extracted following medical indication from German donors and collected between 1997 and 2007 were prepared and irradiated at the Helmholtz Zentrum München. Five out of six samples were irradiated at 0.1, 0.2, 0.5, 1.0 and 1.5 Gy air kerma; and one unirradiated sample was kept as control. The doses delivered to the individual samples were unknown to the participants, who were asked to measure each sample nine times, and to report the EPR signal response, the mass of aliquots measured, and the parameters of EPR signal acquisition and signal evaluation. Critical dose and detection limit were calculated by the organizers on the basis of the calibration-curve parameters obtained at every laboratory. For calibration curves obtained by measuring every calibration sample three times, the mean value of the detection limit was 205 mGy, ranging from 56 to 649 mGy. The participants were also invited to provide the signal response and the nominal dose of their current dose calibration curve (wherever available), the critical dose and detection limit of which were also calculated by the organizers.
AU  - Fattibene, P.*
AU  - Wieser, A.
AU  - Adolfsson, E.*
AU  - Benevides, L.A.*
AU  - Brai, M.*
AU  - Callens, F.*
AU  - Chumak, V.*
AU  - Ciesielski, B.*
AU  - Della Monaca, S.*
AU  - Emerich, K.*
AU  - Gustafsson, H.*
AU  - Hirai, Y.*
AU  - Hoshi, M*
AU  - Israelsson, A.*
AU  - Ivannikov, A.*
AU  - Ivanov, D.*
AU  - Kaminska, J.*
AU  - Wu, Ke.*
AU  - Lund, E.*
AU  - Marrale, M.*
AU  - Martens, L.*
AU  - Miyazawa, C.*
AU  - Nakamura, N.*
AU  - Panzer, W.
AU  - Pivovarov, S.*
AU  - Reyes, R.A.*
AU  - Rodzi, M.*
AU  - Romanyukha, A.A.*
AU  - Rukhin, A.*
AU  - Sholom, S.*
AU  - Skvortsov, V.*
AU  - Stepanenko, V.*
AU  - Tarpan, M.A.*
AU  - Thierens, H.*
AU  - Toyoda, S.*
AU  - Trompier, F.*
AU  - Verdi, E.
AU  - Zhumadilov, K.*
C1  - 6459
C2  - 28728
CY  - Oxford
SP  - 765-771
TI  - The 4th international comparison on EPR dosimetry with tooth enamel. Part 1: Report on the results.
JO  - Radiat. Meas.
VL  - 46
IS  - 9
PB  - Elsevier
PY  - 2011
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Electronic components in portable electronic devices such as mobile phones and portable media player have previously been shown to be useful tools for retrospective and accident dosimetry. In this study the properties of alumina rich inductors removed from mobile phones are investigated using thermoluminescence (TL). The typical glow curve of this component has two main peaks at 170 and 270 °C. With a suitable measurement protocol sensitivity changes of both peaks could be corrected so that the TL signal shows a linear increase in the investigated dose range from 100 mGy to 5 Gy. All inductors studied showed essentially no signal for zero dose. We investigated the fading of the TL signals and the detection limit of inductors extracted from different mobile phones.
AU  - Fiedler, I.
AU  - Woda, C.
C1  - 6372
C2  - 28727
CY  - Oxford
SP  - 1862-1865
TI  - Thermoluminescence of chip inductors from mobile phones for retrospective and accident dosimetry.
JO  - Radiat. Meas.
VL  - 46
IS  - 12
PB  - Elsevier
PY  - 2011
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - The neutron field at the FRM II neutron therapy was characterised by means of a Bonner sphere spectrometer. Inside the therapy room and the adjacent radiography room, gold foils were used in the center of the moderating polyethylene (PE) spheres of the spectrometer, to detect the moderated neutrons. The measured neutron spectra are dominated – as expected – by neutrons with an energy of about 1 MeV. The spectra were in quantitative agreement with those calculated by means of the MCNP code, by Breitkreutz and co-workers. Outside the therapy room, 3He proportional counters were used to detect the neutrons moderated by the PE spheres of the spectrometer. Here, the spectra were much softer and included thermal neutrons as major component. Based on these neutron spectra, the neutron ambient dose equivalent rate View the MathML source was calculated. The resulting View the MathML source values were between 0.92 and 1.68 μSv/h, depending on the position outside the shielding. These values were in close agreement to the one measured by means of the AMIRA tissue-equivalent proportional counter. It is concluded that the neutron spectra at the neutron therapy facility at the new FRM II research reactor at Garching, Germany, are now well characterised.
AU  - Garny, S.
AU  - Mares, V.
AU  - Roos, H.*
AU  - Wagner, F.M.*
AU  - Rühm, W.
C1  - 5319
C2  - 28050
SP  - 92-97
TI  - Measurement of neutron spectra and neutron doses at the Munich FRM II therapy beam with Bonner spheres.
JO  - Radiat. Meas.
VL  - 46
IS  - 1
PB  - Elsevier
PY  - 2011
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - MADEIRA was a Collaborative Project cofunded by the European Commission through the EURATOM Seventh Research Framework Programme. It was structured into four scientific work packages, and its aim was to optimize the efficacy and safety of 3D functional imaging in nuclear medicine and thereby to reduce the radiation exposures of the patients while keeping or even improving the quality of the diagnostic information. Additionally, a fifth work package was dedicated to training and dissemination activities, including the organization of specific training courses, as well as research exchange programs for young scientists. This manuscript summarizes the experience gained during the Training Courses, in particular the one devoted to aspects of radiation protection in nuclear medicine.
AU  - Giussani, A.
AU  - Mattsson, S.*
AU  - Mikuz, M.*
AU  - Cantone, M.C.*
AU  - Hoeschen, C.
AU  - MADEIRA Consortium (*)
C1  - 6610
C2  - 28965
SP  - 1310-1314
TI  - Training activities on radiation protection in nuclear medicine in the frame of the EURATOM FP7 collaborative project MADEIRA.
JO  - Radiat. Meas.
VL  - 46
IS  - 11
PB  - Elsevier
PY  - 2011
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Between 1949 and 1951 about 100 PBq of intermediate and low level liquid radioactive wastes were released into the Techa River (Southern Urals, Russia). To estimate the radiation exposure of Techa River residents having taken place in the past, EPR measurements of tooth enamel were performed. The cumulative dose obtained by EPR, however, is due to both, external photons and internal 90Sr incorporated in enamel and dentin. To provide estimates of the 90Sr content in the teeth tissue, three supplementary methods are used: visualization and mapping of the 90Sr distribution in tooth tissue using Imaging Plates. measurements of the90Sr activity in tooth tissue samples using a β-spectrometer.. measurements of dose rate due to 90Sr in tooth samples using thin-layer Al2O3:C TL dosimeters.
AU  - Semioshkina, N.A.
AU  - Fiedler, I.
AU  - Schillinger, B.*
AU  - Ulanowski, A.
AU  - Potapov, V.*
AU  - Ivanov, O.*
AU  - Wagner, F.M.*
AU  - Gerstmann, U.
C1  - 6371
C2  - 28726
CY  - Oxford
SP  - 1897-1899
TI  - Comparison of three non-destructive methods to measure 90Sr in human tooth samples.
JO  - Radiat. Meas.
VL  - 46
IS  - 12
PB  - Elsevier
PY  - 2011
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - During the long-term study of tooth enamel by EPR dosimetry for population exposed to radiation due to contamination of the Techa River, it was found out that for some of the tooth donors the dose accumulated in tooth enamel could be as high as several tens of Gy. Such doses were absorbed only in tooth enamel and they should not be associated with exposures to other organs or the whole body. The nature of such doses was discussed in a number of previous papers where it was shown that the source of such doses is (90)Sr incorporated in the calcified dental tissues. However, among specialists in radiation dosimetry who were not involved in the biokinetic studies, the nature and dosimetric significance of extra-high doses in tooth enamel are still raising questions. The aim of the current paper is to summarize the accumulated information on extra-high doses in the teeth of the Techa riverside residents, describe the dose levels observed, explain the nature of extra-high doses in the enamel and discuss their informative value. The paper includes an overview of already published findings and an analysis of information collected in the data bank of the Urals Research Center for Radiation Medicine (URCRM), Chelyabinsk, Russia, which has not been published before.
AU  - Shishkina, E.A.*
AU  - Degteva, M.O.*
AU  - Tolstykh, E.I.*
AU  - Volchkova, A.*
AU  - Ivanov, D.V.*
AU  - Wieser, A.
AU  - Della Monaca, S.*
AU  - Fattibene, P.*
C1  - 6839
C2  - 29343
SP  - 760-764
TI  - Extra-high doses detected in the enamel of human teeth in the Techa riverside region.
JO  - Radiat. Meas.
VL  - 46
IS  - 9
PB  - Elsevier
PY  - 2011
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - The EURADOS (European Radiation Dosimetry Group) working group (WG2) on Harmonisation of Individual Monitoring in Europe has shown that intercomparisons are fundamental for harmonisation of individual monitoring. As a result of these considerations, EURADOS started to prepare a series of continuous intercomparisons for individual monitoring services (IMS) in Europe. EURADOS has now successfully executed two intercomparison exercises, one for whole body dosemeters (2008) and one for extremity dosemeters (2009). Both exercises were performed without external funding, all costs being covered by the participants' fees. More than 120 (i) different - mainly passive - dosimetry systems were tested from all over Europe until now and the results were analysed and compared. Although scientific studies were not the primary objective of these exercises specific additional information about the tested systems supplied by the participants for statistical analysis allows a detailed analysis of these results with respect to different parameters like dosemeter type, detector material, filter thickness or others design parameters. The influence of such parameters on the response values of the dosemeters is analysed and discussed in this paper. Both energy response as well as directional response for beta and photon radiation are considered. The influence of different design parameters e.g. detector material, is analysed by comparing the frequency distribution of the response values for different dosemetergroups. Pronounced differences for different detector materials (LiF:Mg,Ti, LiF:Mg,Cu,P and Li2B4O7/CaSO4) were found. The paper gives a comprehensive overview on the performance of various European dosimetry services and the influence of the dosemeter design on the resulting response values.
AU  - Stadtmann, H.*
AU  - Grimbergen, T.W.M.*
AU  - Figel, M.
AU  - Romero, A.M.*
AU  - McWhan, A.F.*
C1  - 7253
C2  - 29613
SP  - 1829-1834
TI  - EURADOS intercomparisons on whole body and extremity dosemeters (2008-2009) - results and comparison of different dosemeter designs.
JO  - Radiat. Meas.
VL  - 46
IS  - 12
PB  - Elsevier
PY  - 2011
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Between 1949 and 1956 the Techa River (Southern Urals, Russia) was contaminated as a result of releases of radioactive waste by the Mayak Production Association. EPR dosimetry with tooth enamel has been used to estimate the external exposure of Techa riverside residents over the last 17 years. The database "Tooth" of the Urals Research Center for Radiation Medicine (URCRM) has accumulated about 1000 EPR measurements of tooth enamel from the rural population of the Urals region. The teeth were investigated by laboratories of Russia, USA, Germany and Italy. Most of the enamel samples were measured several times in different laboratories. Each laboratory used different equipment and its own methods for sample preparation and EPR spectra analysis. Even measurements performed at the same laboratory over 10-15 years may not be assumed as uniform: methods change with time, and equipment is subject to aging. These two factors influenced EPR performance. The purpose of this study is, therefore, the harmonization of EPR data accumulated during long-term dosimetric investigations in the Southern Urals for further pooled analysis. The results will be used for external dose evaluation in the Techa River region.
AU  - Volchkova, A.*
AU  - Shishkina, E.A.*
AU  - Ivanov, D.*
AU  - Timofeev, Y.*
AU  - Fattibene, P.*
AU  - Della Monaca, S.*
AU  - Wieser, A.
AU  - Degteva, M.O.*
C1  - 6840
C2  - 29344
SP  - 801-807
TI  - Harmonization of dosimetric information obtained by different EPR methods: Experience of the Techa River study.
JO  - Radiat. Meas.
VL  - 46
IS  - 9
PB  - Elsevier
PY  - 2011
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - The nuclear workers of the Mayak Production Association had regular check-ups including medical diagnostic X-ray examinations since start of the production lines in 1948. Doses from diagnostic examinations need to be considered in reconstruction of occupational doses of the workers with electron paramagnetic resonance (EPR) of tooth enamel. The numbers and types of examinations of an individual worker can be assessed from the Mayak PA archives but no information was available on doses delivered to teeth by a single specific examination. Of the twenty one applied examination procedures only three affected the teeth, these being X-ray examinations of teeth, skull and cervical spine. For these three kinds of examinations operational procedures and operating modes of X-ray units were compiled from the archive and photon spectra were obtained from a catalog of spectral data for diagnostic X-rays. Entrance doses in air kerma were calculated using the fluence of photon spectra and absorbed dose in tooth enamel for various tooth positions and exposure geometry was then calculated using dose conversion coefficients obtained from Monte Carlo simulations. Doses were calculated for examinations in 1948–2000. Except for examination of the skull, absorbed doses in enamel of incisors were found to be about twice as large as in enamel of molars. In the period before 1970 the largest mean absorbed doses in tooth enamel were due to X-ray examination of teeth, with 64 mGy and 34 mGy calculated for incisors and molars, respectively. In the same period the lowest mean doses were due to X-ray examination of the skull, with 11 mGy and 12 mGy calculated for incisors and molars, respectively. In the period from 1970 to 2000, largest mean doses in enamel were due to X-ray examination of cervical spine, with 23 mGy and 12 mGy calculated for incisors and molars, respectively.
AU  - Wieser, A.
AU  - Vasilenko, E.*
AU  - Zankl, M.
AU  - Greiter, M.
AU  - Ulanowski, A.
AU  - Sabayev, A.*
AU  - Knyazev, V.*
AU  - Zahrov, P.*
C1  - 6370
C2  - 28725
CY  - Oxford
SP  - 808-812
TI  - Evaluation of dose to tooth enamel from medical diagnostic X-ray examinations at Mayak PA.
JO  - Radiat. Meas.
VL  - 46
IS  - 9
PB  - Elsevier
PY  - 2011
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Optically stimulated luminescence (OSL) dosimetry is applied to quartz extracted from bricks from a mill in a contaminated village (Muslyumovo) of the Techa River valley, Southern Urals, Russia, for the purpose of dose reconstruction. Previous works [Goksu et al., 2002. First international intercomparison of luminescence techniques using samples from the Techa river valley. Health Phys. 82, 94-101] have shown that the expected dose due to man-made sources of radiation in the bricks is in the same range as the background dose due to natural sources of radiation, therefore a precise estimate of the cumulative and background dose is of utmost importance. Cumulative doses could be assessed with OSL with a precision of around 4% and lie between 450 and 600 mGy. The background dose was carefully determined by a combination of laboratory measurements, in-situ gamma spectrometry and Monte Carlo modelling. The results show that the gamma-dose rate of the soil was overestimated and the fractional brick gamma-dose rate underestimated in previous studies, but that the overall gamma-dose rate was nearly correct, due to mutual compensation. The obtained anthropogenic doses in brick measured with OSL lie between 200 and 300 mGy, show variability between adjacent bricks within error limits for one spot but a significant difference for two samples is observed for another spot. A distinct dependency of measured dose upon sample height is observed, which is an indication of a source distribution, which extends over a large area and up to a certain depth into the soil and in which higher contaminated areas are located at a greater distance to the mill than lower contaminated areas. A measured dose depth profile is compared with previously published Monte Carlo calculations to verify the source energy.
AU  - Woda, C.
AU  - Ulanowski, A.
AU  - Bougrov, N.G.*
AU  - Fiedler, I.
AU  - Degteva, M.O.*
AU  - Jacob, P.
C1  - 6347
C2  - 28724
CY  - Oxford
SP  - 277-285
TI  - Luminescence dosimetry in a contaminated settlement of the Techa River valley, Southern Urals, Russia.
JO  - Radiat. Meas.
VL  - 46
IS  - 3
PB  - Pergamon-Elsevier Science
PY  - 2011
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - The potential of the 210 degrees C Thermoluminescence (TL) peak in quartz for accurate dose reconstruction is studied by comparative TL and optically simulated luminescence (OSL) measurements on quartz extracted from bricks from a mill in a contaminated village of the Techa River valley, Southern Urals, Russia. The cumulative doses measured with TL were found to be continuously lower (on average 10 -20%) than the ones measured with OSL for the same sample and using the same luminescence reader From dose recovery tests, laboratory kinetic analysis and available meteorological parameters of the sample site for the past 100 years, it is concluded that the most likely reason for the discrepancy is thermal fading of the 210 degrees C TL peak. By applying a suitable model, an effective lifetime of the electron trap of the 210 degrees C TL peak of 200-700 years is estimated for the moderate continental climate at the sample site. It is concluded that for samples in regions of continental climate and directly exposed to sunlight, dose measurements using the 210 degrees C TL peak should be restricted to the last 50-60 years. Applications to older samples should only be considered if bricks are not directly exposed to sunlight or if the background dose is small compared to the anthropogenic dose, as the latter will have been acquired during shorter times and will thus not have been subjected to significant thermal fading.
AU  - Woda, C.
AU  - Ulanowski, A.
AU  - Bougrov, N.G.*
AU  - Fiedler, I.
AU  - Degteva, M.O.*
AU  - Jacob, P.
C1  - 6410
C2  - 28626
SP  - 485-493
TI  - Potential and limitations of the 210° C TL peak in quartz for retrospective dosimetry.
JO  - Radiat. Meas.
VL  - 46
IS  - 5
PB  - Elsevier
PY  - 2011
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Cosmic particle flux is significantly higher onboard aircraft than at ground level and for this reason the aircraft crews in the European Union and Japan have been recognized as occupationally exposed workers. Since the radiation field at aviation altitude is very complex in terms of particle composition and particle energies, the dose assessment is a very difficult task. The dose is usually estimated using numerical codes validated by experimental data. In this paper, a comparison of two codes is presented, EPCARD.Net and JISCARD EX. Doses due to the Galactic Cosmic Rays (GCRs) are provided for periods close to solar maximum and minimum and for selected 68 flights covering major commercial routes in the world. The overall agreement between the codes is much better than ±20%. The agreement within the codes is considered to be fully satisfactory for radiation protection purposes.
AU  - Mares, V.
AU  - Yasuda, H.*
C1  - 5371
C2  - 28716
SP  - 1553-1556
TI  - Aviation route doses calculated with EPCARD.Net and JISCARD EX.
JO  - Radiat. Meas.
VL  - 45
IS  - 10
PB  - Elsevier
PY  - 2010
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Monte Carlo (MC) codes for neutron transport calculations such as MCNP, MCNPX, FLUKA, PHITS, and GEANT4, crucially rely on cross sections that describe the interaction of neutrons with nuclei. For neutron energies below 20 MeV, evaluated cross sections are available that are validated against experimental data. In contrast, for high energies (above 20 MeV) experimental data are scarce and, for this reason, every neutron transport code is based on theoretical nuclear models to describe interactions of neutrons with nuclei in matter. Here we report on the calculation of a complete set of response functions for a Bonner spheres spectrometer (BSS), by means of GEANT4 using the Bertini and Binary Intranuclear Cascade (INC) models for energies above 20 MeV. The recent results were compared with those calculated by MCNP/LAHET and MCNP/HADRON MC codes. It turns out that, whatever code used, the response functions were rather similar for neutron energies below 20 MeV, for all 16 detector/moderator combinations of the considered BSS system. For higher energies, however, differences of more than a factor of 2 were observed, depending on neutron energy, detector/moderator combination, MC code, and nuclear model used. These differences are discussed in terms of neutron fluence rates measured at the environmental research station (UFS), “Schneefernerhaus”, (Zugspitze mountain, Germany, 2650 m a.s.l.) for energies below 0.4 eV (thermal neutrons), between 0.4 eV and 100 keV (epithermal neutrons), between 100 keV and 20 MeV (evaporation neutrons), and above 20 MeV (cascade neutrons). In terms of total neutron fluence rates, relative differences of up to 4% were obtained when compared to the standard MCNP/LAHET results, while in terms of total ambient dose equivalent, relative differences of up to 8% were obtained. Both the GEANT4 Binary INC and Bertini INC gave somewhat larger fluence and dose rates in the epithermal region. Most relevant for dose, however, those response functions calculated with the GEANT4 Bertini INC model provided about 18% less neutrons in the cascade region, which led to a roughly 13% smaller contribution of these neutrons to ambient dose equivalent. It is concluded that doses from secondary neutrons from cosmic radiation as deduced from BSS measurements are uncertain by about 10%, simply because of some differences in nuclear models used by various neutron transport codes.
AU  - Pioch, C.
AU  - Mares, V.
AU  - Rühm, W.
C1  - 4677
C2  - 27812
SP  - 1263-1267
TI  - Influence of Bonner sphere response functions above 20 MeV on unfolded neutron spectra and doses.
JO  - Radiat. Meas.
VL  - 45
IS  - 10
PB  - Elsevier
PY  - 2010
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Since many decades, Bonner sphere spectrometers (BSSs) are routinely used for assessment of neutron spectra over a wide energy range from some meV to GeV. Typically, a spectrometer consists of a neutron detector sensitive to thermal neutrons located inside moderating polyethylene (PE) spheres of various sizes. Based on the response functions of the detector/sphere systems that must be calculated by Monte Carlo codes, an unfolding procedure is applied to deduce the present neutron spectrum from the count rates of the detectors. To start the unfolding procedure, a guess spectrum is required that includes some prior information on the physics of the investigated neutron spectrum, and that is iteratively modified to match the measured count rates. For the present investigation, a BSS-system consisting of an 3He proportional counter and seventeen spheres containing PE or a combination of PE and lead is used. The system is used for example to measure secondary neutrons from cosmic radiation at mountain altitudes, or from high-energy accelerators outside the radiation shielding. A systematic study was performed to quantify the influence of the chosen guess spectrum and the number of iteration steps on the unfolded neutron spectrum, and on integral quantities deduced such as total neutron fluence or ambient dose equivalent. It turned out that none of these changes resulted in dose quantities that were more than a few percent different to those deduced when the optimised start spectrum was used. Similarly, use of the two different response matrices available for our BSS system provided similar values for the ambient dose equivalent.
AU  - Simmer, G.
AU  - Mares, V.
AU  - Weitzenegger, E.
AU  - Rühm, W.
C1  - 251
C2  - 27055
SP  - 1-9
TI  - Iterative unfolding for Bonner sphere spectrometers using the MSANDB code - sensitivity analysis and dose calculation.
JO  - Radiat. Meas.
VL  - 45
IS  - 1
PB  - Elsevier
PY  - 2010
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - The shape of the OSL decay curve and the effect of longer time delays between accidental exposure and readout of alumina-rich electronic components from portable electronic devices are investigated. The OSL decay curve follows a hyperbolic decay function, which is interpreted as an approximation of several closely spaced or even a continuous distribution of single trap OSL decay functions. Longer time delays between exposure and readout lead to a rising dose vs. OSL integration time plot, when applying a low preheat. Supplementary TL investigations indicate a distribution in activation energies for the main dosimetric (190 degrees C) peak and that the lower temperature part could fade with a higher rate than the higher temperature part. Consequences for the applied preheat treatment prior to dose measurement are discussed.
AU  - Woda, C.
AU  - Greilich, S.*
AU  - Beerten, K.*
C1  - 5957
C2  - 27665
SP  - 746-748
TI  - On the OSL curve shape and preheat treatment of electronic components from portable electronic devices.
JO  - Radiat. Meas.
VL  - 45
IS  - 3-6
PB  - Elsevier
PY  - 2010
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Owing to the existence of ceramic materials inside common personal objects Such as cellular phones and USB flash drives, these objects may be very useful in emergency (accident) dosimetry. Here we will present initial results regarding the dosimetric properties as determined by thermoluminescence (TL) from two alumina-rich electronic components from a USB flash drive. The TL method was applied in order to investigate the potential of conventional TL equipment for such purposes. For comparison, the optically stimulated luminescence (OSL) of the components was investigated as well. The studied components are ceramic resonators and alumina-based substrates from electrical resistors. The results show that various TL-related properties such as fading, optical stability and zero-dose response are different for the two investigated components. On the basis of these properties, the ceramic resonator was selected for dose recovery tests using TL and OSL The given dose could reliably be determined using both methods, assuming that prompt measurement and/or fading correction is possible.
AU  - Beerten, K.
AU  - Woda, C.
AU  - Vanhavere, F.
C1  - 2242
C2  - 26549
CY  - Oxford
SP  - 620-625
TI  - Thermoluminescence dosimetry of electronic components from personal objects.
JO  - Radiat. Meas.
VL  - 44
IS  - 5-6
PB  - Pergamon, Elsevier Science
PY  - 2009
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - The European Commission has funded within its 6th Framework Programme a three-year project (2005-2007) called CONRAD, COordinated Network for RAdiation Dosimetry. The organizational framework for this project was provided by the European radiation Dosimetry Group EURADOS. Work Package 6 of CONRAD dealt with 'complex mixed radiation fields at workplaces' and in this context it organised a benchmark exercise, which included both measurements and calculations, in a stray radiation field at a high-energy particle accelerator at GSI, Germany. The aim was to intercompare the response of several types of active detectors and passive dosemeters in a well-characterised workplace field. The Monte Carlo simulations of the radiation field and the experimental determination of the neutron spectra with various Bonner Sphere Spectrometers are discussed in Rollet et al. (2008) and in Wiegel et al. (2008). This paper focuses on the intercomparison of the response of the dosemeters in terms of ambient dose equivalent. The paper describes in detail the detectors employed in the experiment, followed by a discussion of the results. A comparison is also made with the H*(10) values predicted by the Monte Carlo simulations and those measured by the BSS systems.
AU  - Silari, M.*
AU  - Agosteo, S.*
AU  - Beck, P.*
AU  - Bedogni, R.*
AU  - Cale, E.*
AU  - Caresana, M.*
AU  - Domingo, C.*
AU  - Donadille, L.*
AU  - Dubourg, N.*
AU  - Esposito, A.*
AU  - Fehrenbacher, G.
AU  - Fernández, F.*
AU  - Ferrarini, M.*
AU  - Fiechtner, A.*
AU  - Fuchs, A.*
AU  - García, M.J.*
AU  - Golnik, N.*
AU  - Gutermuth, F.*
AU  - Khurana, S.*
AU  - Klages, Th.*
AU  - Latocha, M.*
AU  - Mares, V.
AU  - Mayer, S.*
AU  - Radon, T.*
AU  - Reithmeier, H.*
AU  - Rollet, S.*
AU  - Roos, H.*
AU  - Rühm, W.
AU  - Sandri, S.*
AU  - Schardt, D.*
AU  - Simmer, G.
AU  - Spurný, F.*
AU  - Trompier, F.*
AU  - Villa-Grasa, C.*
AU  - Weitzenegger, E.
AU  - Wiegel, B.*
AU  - Wielunski, M.
AU  - Wissmann, F.*
AU  - Zechner, A.*
AU  - Zielczynski, M.*
C1  - 435
C2  - 26594
CY  - Oxford
SP  - 673-691
TI  - Intercomparison of radiation protection devices in a high-energy stray neutron field. Part III: Instrument response.
JO  - Radiat. Meas.
VL  - 44
IS  - 7-8
PB  - Elsevier
PY  - 2009
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - The European Commission has funded within its 6th Framework Programme a three-year project (2005-2007) called CONRAD, COordinated Network for RAdiation Dosimetry. A major task of the CONRAD Work Package 'complex mixed radiation fields at workplaces' was to organise a benchmark exercise in a workplace field at a high-energy particle accelerator where neutrons are the dominant radiation component. The CONRAD benchmark exercise took place at the Gesellschaft fur Schwerionenforschung mbH (GSI) in Darmstadt, Germany in July 2006. In this paper, the results of the spectrometry using four extended -range Bonner sphere spectrometers of four different institutes are reported. Outside Cave A the neutron spectra were measured with three spectrometers at six selected positions and ambient dose equivalent values were derived for use in the intercomparison with other area monitors and dose, meters. At a common position all three spectrometers were used to allow a direct comparison of their, results which acts as an internal quality assurance. The comparison of the neutron spectra measured by the different groups shows very good agreement. A detailed analysis presents some differences between the shapes of the spectra and possible sources of these differences are discussed. However, the ability of Bonner sphere spectrometers to provide reliable integral quantities like fluence and ambient dose equivalent is well demonstrated in this exercise. The fluence and dose results derived by the three groups agree very well within the given uncertainties, not only with respect to the total energy region present in this environment but also for selected energy regions which contribute in certain strength to the total values. In addition to the positions outside Cave A one spectrometer was used to measure the neutron spectrum at one position in the entry maze of Cave A. In this case a comparison was possible to, earlier measurements.
AU  - Wiegel, B.*
AU  - Agosteo, S.*
AU  - Bedogni, R.*
AU  - Caresana, M.*
AU  - Esposito, A.*
AU  - Fehrenbacher, G.*
AU  - Ferrarini, M.*
AU  - Hohmann, E.*
AU  - Hranitzky, C.*
AU  - Kasper, A.*
AU  - Khurana, S.*
AU  - Mares, V.
AU  - Reginatto, M.*
AU  - Rollet, S.*
AU  - Rühm, W.
AU  - Schardt, D.*
AU  - Silari, M.*
AU  - Simmer, G.
AU  - Weitzenegger, E.
C1  - 434
C2  - 26593
CY  - Oxford
SP  - 660-672
TI  - Intercomparison of radiation protection devices in a high-energy stray neutron field, Part II: Bonner sphere spectrometry.
JO  - Radiat. Meas.
VL  - 44
IS  - 7-8
PB  - Elsevier
PY  - 2009
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - The potential of optically stimulated luminescence of wire-bond chip card modules, used in health insurance, ID, cash and credit cards for retrospective and accident dosimetry is investigated. Chip card modules obtained directly from the producer, using a widely spread UV-cured epoxy product for encapsulation, are used as basis for the study. The radiation sensitivity is due to silica grains added to the epoxy for controlling the thixotropic properties. Luminescence properties are complex due to the presumed thermo-optical release of electrons from the epoxy and transfer into the silica. Best results and highest sensitivity are obtained by using no or only low preheat treatments. A high degree of fading of the OSL signal during storage at room temperature is observed, which is tentatively explained by the superposition of thermal decay of shallow OSL traps and athermal (anomalous) decay of deeper OSL traps. The dose response of the OSL signal shows exponentially saturating behaviour, with saturation doses of 77 Gy or 9.6 Gy, depending on pretreatment. Dose recovery tests show that given doses can be recovered within a deviation of +/- 14%, if measured signals are corrected for fading. The minimum detectable dose is estimated at similar to 3 mGy, similar to 10 mGy and similar to 20 mGy for readouts immediately, 1 day and 10 days after exposure, respectively.
AU  - Woda, C.
AU  - Spöttl, T.
C1  - 922
C2  - 26550
CY  - Oxford
SP  - 548-553
TI  - On the use of OSL of wire-bond chip card modules for retrospective and accident dosimetry.
JO  - Radiat. Meas.
VL  - 44
IS  - 5-6
PB  - Pergamon, Elsevier Science
PY  - 2009
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - This communication summarizes the results concerning the Monte Carlo (MC) modelling of Germanium detectors for the measurement of low energy photons arising from the “International comparison on MC modelling for in vivo measurement of Americium in a knee phantom” organized within the EU Coordination Action CONRAD (Coordinated Network for Radiation Dosimetry) as a joint initiative of EURADOS working groups 6 (computational dosimetry) and 7 (internal dosimetry). MC simulations proved to be an applicable way to obtain the calibration factor that needs to be used for in vivo measurements.
AU  - Gómez-Ros, J.M.*
AU  - de Carlan, L.*
AU  - Franck, D.*
AU  - Gualdrini, G.*
AU  - Lis, M.*
AU  - López, M.A.*
AU  - Moraleda, M.*
AU  - Zankl, M.
AU  - Badal, A.*
AU  - Capello, K.*
AU  - Cowan, P.*
AU  - Ferrari, P.*
AU  - Heide, B.*
AU  - Henniger, J.*
AU  - Hooley, V.*
AU  - Hunt, J.*
AU  - Kinase, S.*
AU  - Kramer, G.H.*
AU  - Löhnert, D.*
AU  - Lucas, S.*
AU  - Nuttens, V.*
AU  - Packer, L.W.*
AU  - Reichelt, U.*
AU  - Vrba, T.*
AU  - Sempau, J.*
AU  - Zhang, B.*
C1  - 174
C2  - 25360
SP  - 510-515
TI  - Monte Carlo modelling of Germanium detectors for the measurement of low energy photons in internal dosimetry: Results of an international comparison.
JO  - Radiat. Meas.
VL  - 43
IS  - 2-6
PB  - Elsevier
PY  - 2008
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Results are presented for electron paramagnetic resonance (EPR) dosimetry with tooth enamel that focus on the dose region below 100 mGy. Three uncontaminated molars were gamma-irradiated in steps of 10–100 mGy and then in larger steps to 400 mGy. The spectra were evaluated using a deconvolution method including a simulated powder spectrum for extracting the dose related EPR signal of tooth enamel. The dose related signal intensity and the variability between samples were evaluated to investigate the feasibility to reconstruct irradiation doses below 100 mGy. Averaged signal amplitudes as well as the signal amplitudes for single sample were analysed. The performance parameters, critical dose and limit of detection, were calculated and compared with the averaged signal amplitudes of sets of five samples of a pool of mixed tooth samples originating from the same source but irradiated from 100 to 1500 mGy. The values of performance parameters were found to depend on the number and type of samples included in assessment. The evaluated critical dose varied between 131 and 50 mGy for measurements of single sample, and 73 and 33 mGy for average amplitudes of three and five samples, respectively. For exposures below 100 mGy the dose related EPR-signal amplitude was found to correlate with the applied dose only for one of three samples for which the evaluated critical dose was 50 mGy.
AU  - Güttler, A.
AU  - Wieser, A.
C1  - 3245
C2  - 25411
SP  - 819-822
TI  - EPR-dosimetry with tooth enamel for low doses.
JO  - Radiat. Meas.
VL  - 43
IS  - 2-6
PB  - Elsevier
PY  - 2008
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - A new electronic meter for personal radon exposures was developed and several prototypes were built. The exposure meter is optimized with respect to short-term (days) and long-term (View the MathML source) measurements of indoor radon concentrations and personal radon exposure. The exposure meter records measured concentration levels in adjustable time intervals allowing a time resolved analysis.
AU  - Karinda, F.L.
AU  - Haider, B.
AU  - Rühm, W.
C1  - 1696
C2  - 25202
SP  - 1170-1174
TI  - A new electronic personal exposure meter for radon gas.
JO  - Radiat. Meas.
VL  - 43
IS  - 2-6
PB  - Elsevier
PY  - 2008
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Thermoluminescence-based beta dosimetry, previously proposed for the estimate of the internal contamination in teeth, and EPR has been used in this paper to investigate the homogeneity of 90Sr contamination and of dose within nine teeth of one person born in the year of the onset of waterborne radioactive releases of the Mayak plutonium facility. A large deviation of dose and activity distributions in both enamel and radical dentine of the various teeth was observed. Average dose was View the MathML source in enamel and View the MathML source in radical dentine. Average 90Sr concentration was View the MathML source in enamel and View the MathML source in radical dentine. The observed deviation around the mean value of dose and 90Sr concentration can be explained due to the specific mineral evolution of each tooth at the time of Sr intake. In the same donor, a negative correlation was also observed between radical dentine and enamel for the 90Sr specific activity as well for the dose.
AU  - Veronese, I.*
AU  - Fattibene, P.*
AU  - Cantone, M.C.*
AU  - de Coste, V.*
AU  - Giussani, A.
AU  - Onori, S.*
AU  - Shishkina, E.A.*
C1  - 1694
C2  - 25298
SP  - 813-818
TI  - EPR and TL-based beta dosimetry measurements in various tooth components contaminated by 90Sr.
JO  - Radiat. Meas.
VL  - 43
IS  - 2-6
PB  - Elsevier
PY  - 2008
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - Electronic personal neutron dosimeters developed at GSF, PTB, and LMU, were exposed with mono-energetic neutrons at the PTB neutron irradiation facility in Braunschweig, Germany. The neutron energies used ranged from 1.5 to 4.1 MeV. The doses measured by each dosimeter were compared to each other and to the Saphydose-n dosimeter that is commercially available. All dosimeters were calibrated based on either 252Cf and/or 241Am–Be neutron sources or a 60Co secondary standard reference field. The doses measured were compared to estimates of reference values based on a long counter. Generally, all dosimeters produced reasonable results, given the uncertainties involved. It was noticed that the dosimeter responses show slight dependencies on energy. The corresponding differences are summarised and discussed.
AU  - Wielunski, M.
AU  - Wahl, W.
AU  - El-Faramawy, N.A.
AU  - Rühm, W.
AU  - Luszik-Bhadra, M.*
AU  - Roos, H.*
C1  - 1695
C2  - 25301
SP  - 1063-1067
TI  - Intercomparison exercise with MeV neutrons using various electronic personal dosimeters.
JO  - Radiat. Meas.
VL  - 43
IS  - 2-6
PB  - Elsevier
PY  - 2008
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - In the framework of a comparison between three laboratories, electron paramagnetic resonance (EPR) signal-to-dose response curves were measured for sets of 30 tooth enamel samples and the variance of EPR measurements in dependence on absorbed dose was evaluated, in nine combinations of laboratory of sample preparation and EPR evaluation, respectively. As a test for benchmarking of EPR evaluation, the parameters ‘critical dose’ and ‘limit of detection’ were proposed as performance parameters following definitions from chemical-metrology, and a model function was suggested for analytical formulation of the dependence of the variance of EPR measurement on absorbed dose. First estimates of limits of detection by weighted and unweighted fitting resulted in the range 101–552 and 67–561 mGy, respectively, and were generally larger with weighted than with unweighted fitting. Indication was found for the influence of methodology of sample preparation and applied EPR measurement parameters on performance of EPR dosimetry with tooth enamel.
AU  - Wieser, A.
AU  - Fattibene, P.*
AU  - Shiskina, E.A.*
AU  - Ivanov, D.V.*
AU  - de Coste, V.*
AU  - Güttler, A.
AU  - Onori, S.*
C1  - 3246
C2  - 25486
SP  - 731-736
TI  - Assessment of performance parameters for EPR dosimetry with tooth enamel.
JO  - Radiat. Meas.
VL  - 43
IS  - 2-6
PB  - Elsevier
PY  - 2008
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - The applicability of an objective methodology for dose distribution analysis proposed by Lepper and McKeever [2002. An objective methodology for dose distribution analysis. Radiat. Prot. Dosimetry 101 (1–4), 349–352] to samples, where available material only allows the measurement of a small number of aliquots, is investigated. The basis for the study are artificially and naturally insufficiently bleached samples for which a large number (>90) of aliquots were measured. Smaller sets of aliquots are then randomly drawn from this pool and a Gaussian function fitted to the rising limb of the dose distribution. It is found that when the method is based on a three-parameter fit, it is no longer applicable when the number of aliquots is significantly reduced. The percentage of successful fits for data sets made of only 20 aliquots was on average below 20%. In addition for data sets composed of 40 to 60 aliquots, palaeodoses obtained from fitting spread over a large dose range and showed a strongly asymmetric distribution. A significant improvement could be achieved by fixing the center of the Gaussian function to the mode DE bin and only fitting a two-parameter function to the data sets. With this approach an 80% change of successful fitting could be achieved even when using dose distributions constructed from only 20 to 30 aliquots. The median of the palaeodose distributions was approximately independent of the number of aliquots used. The modified method is then applied to samples from a sedimentary record in the northern Oman mountain range and the results compared with the method proposed by Fuchs and Lang [2001. OSL dating of coarse-grain fluvial quartz using single-aliquot protocols on sediments from NE Peleponnese, Greece. Quat. Sci. Rev. 20, 783–787]. It is concluded that the leading edge method proposed by Lepper and McKeever can be useful to derive DE's from insufficiently bleached sediments even for a small number of aliquots if the Gaussian function is fitted as a two-parameter function.
AU  - Woda, C.
AU  - Fuchs, M.*
C1  - 2720
C2  - 25167
SP  - 26-37
TI  - On the applicability of the leading edge method to obtain equivalent doses in OSL dating and dosimetry.
JO  - Radiat. Meas.
VL  - 43
IS  - 1
PB  - Elsevier
PY  - 2008
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - For intercomparison of methods of dose determination using electron paramagnetic resonance (EPR) spectroscopy of tooth enamel, the same sets of enamel samples were analyzed in different laboratories using similar recording parameters. The sets of samples included calibration samples irradiated in known doses, test samples irradiated to doses unknown to the participants and accidental dose samples prepared from teeth of humans affected by radioactive fallout from nuclear tests in the Semipalatinsk Nuclear Test Site in Kazakhstan. The test samples were analyzed to determine the differences in the resulting doses using different spectrometers and different spectra processing methods. The accidental dose samples were analyzed in order to test the precision of doses determined by EPR spectroscopy and to obtain more accurate values by averaging the results from different laboratories.
AU  - Hoshi, M.*
AU  - Toyoda, S.*
AU  - Ivannikov, A.*
AU  - Zhumadilov, K.*
AU  - Fukumura, A.*
AU  - Apsalikov, K.*
AU  - Zhumadilov, Z.S.*
AU  - Bayankin, S.*
AU  - Chumak, V.*
AU  - Ciesielski, B.*
AU  - de Coste, V.*
AU  - Endo, S.*
AU  - Fattibene, P.*
AU  - Ivanov, D.*
AU  - Mitchell, C.A.*
AU  - Onori, S.*
AU  - Penkowski, M.*
AU  - Pivovarov, S.P.*
AU  - Romanyukha, A.*
AU  - Rukhin, A.B.*
AU  - Schultka, K.*
AU  - Seredavina, T.A.*
AU  - Sholom, S.*
AU  - Skvortsov, V.*
AU  - Stepanenko, V.*
AU  - Tanaka, K.*
AU  - Trompier, F.*
AU  - Wieser, A.
AU  - Wolakiewicz, G.*
C1  - 2701
C2  - 24982
SP  - 1005-1014
TI  - Interlaboratory comparison of tooth enamel dosimetry on Semipalatinsk region : Part 1, general view.
JO  - Radiat. Meas.
VL  - 42
IS  - 6-7
PB  - Elsevier
PY  - 2007
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - In order to investigate the effects of spectrum processing procedures on the results of dose determination using EPR spectroscopy of human tooth enamel, spectra of the same samples measured in different laboratories in the course of the intercomparison were processed by some of the participants using their own unique procedures. Spectra of samples irradiated to known doses (calibration samples) and of samples irradiated to doses unknown to the participants (test samples) were analyzed. By comparison of the results obtained using different spectrum processing methods, it is shown that the precision of calibration and the accuracy of dose determination may be improved by appropriate choice of spectrum processing procedure.
AU  - Ivannikov, A.*
AU  - Toyoda, S.*
AU  - Hoshi, M.*
AU  - Zhumadilov, K.*
AU  - Fukumura, A.*
AU  - Apsalikov, K.*
AU  - Zhumadilov, Z.S.*
AU  - Bayankin, S.*
AU  - Chumak, V.*
AU  - Ciesielski, B.*
AU  - de Coste, V.*
AU  - Endo, S.*
AU  - Fattibene, P.*
AU  - Ivanov, D.*
AU  - Mitchell, C.A.*
AU  - Nalapko, M.*
AU  - Onori, S.*
AU  - Penkowski, M.*
AU  - Pivovarov, S.P.*
AU  - Romanyukha, A.*
AU  - Rukhin, A.B.*
AU  - Sanin, D.*
AU  - Schultka, K.*
AU  - Seredavina, T.A.*
AU  - Sholom, S.*
AU  - Skvortsov, V.*
AU  - Stepanenko, V.*
AU  - Tanaka, K.*
AU  - Trompier, F.*
AU  - Wieser, A.
AU  - Wolakiewicz, G.*
C1  - 2372
C2  - 24983
SP  - 1015-1020
TI  - Interlaboratory comparison of tooth enamel dosimetry on Semipalatinsk region : Part 2, Effects of spectrum processing.
JO  - Radiat. Meas.
VL  - 42
IS  - 6-7
PB  - Elsevier
PY  - 2007
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - The utility of ID card chip modules to function as a radiation dosimeter is investigated. Specifically the thermoluminescence (TL) and optically stimulated luminescence (OSL) of a sampling of chip modules are measured over the range of 0.4–12 Gy. Both infrared (830 nm) from a laser diode and blue light (470 nm) from LEDs were used to perform the OSL measurements. The TL measurements showed a linear dose–response relationship, but the TL suffered from a large zero-dose signal in the unirradiated samples and dose regeneration with time after heating the chip modules. The OSL measurements also showed a linear dose–response, but did not exhibit a zero-dose signal or regeneration. Performing the infrared OSL measurements at a temperature of Click to view the MathML source may improve the dose sensitivity to 0.15 Gy, but the dose–response is supralinear in the dose range investigated. Curve fitting of infrared and blue stimulated luminescence curves showed that both exhibit a fast and a slow component. Thermal stability studies indicates the presence of a component that decays in the first hour of irradiation, and a component that is stable at least during the period of investigation (up to 10 h). This stable component is more appropriate for dosimetry purposes.
AU  - Mathur, V.K.*
AU  - Barkyyoumb, J.H.*
AU  - Yukihara, E.G.*
AU  - Göksu, H.Y.
C1  - 4504
C2  - 24382
SP  - 43-48
TI  - Radiation sensitivity of memory chip module of an ID card.
JO  - Radiat. Meas.
VL  - 42
IS  - 1
PB  - Elsevier
PY  - 2007
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - The requirements for biodosimetric techniques used at long times after exposure, i.e., 6 months to more than 50 years, are unique compared to the requirements for methods used for immediate dose estimation. In addition to the fundamental requirement that the assay measures a physical or biologic change that is proportional to the energy absorbed, the signal must be highly stable over time to enable reasonably precise determinations of the absorbed dose decades later. The primary uses of these biodosimetric methods have been to support long-term health risk (epidemiologic) studies or to support compensation (damage) claims. For these reasons, the methods must be capable of estimating individual doses, rather than group mean doses. Even when individual dose estimates can be obtained, inter-individual variability remains as one of the most difficult problems in using biodosimetry measurements to rigorously quantify individual exposures. Other important criteria for biodosimetry methods include obtaining samples with minimal invasiveness, low detection limits, and high precision. Cost and other practical limitations generally prohibit biodosimetry measurements on a large enough sample to replace analytical dose reconstruction in epidemiologic investigations. However, these measurements can be extremely valuable as a means to corroborate analytical or model-based dose estimates, to help reduce uncertainty in individual doses estimated by other methods and techniques, and to assess bias in dose reconstruction models. There has been extensive use of three biodosimetric techniques in irradiated populations: EPR (using tooth enamel), FISH (using blood lymphocytes), and GPA (also using blood); these methods have been supplemented with luminescent methods applied to building materials and artifacts. A large number of investigations have used biodosimetric methods many years after external and, to a lesser extent, internal exposure to reconstruct doses received from accidents, from occupational exposures, from environmental releases of radioactive materials, and from medical exposures. In most applications, the intent has been to either identify highly exposed persons or confirmed suspected exposures. Improvements in methodology, however, have led many investigators to attempt quantification of whole-body doses received, or in a few instances, to estimate organ doses. There will be a continued need for new and improved biodosimetric techniques not only to assist in future epidemiologic investigations but to help evaluate the long-term consequences following nuclear accidents or events of radiologic terrorism.
AU  - Simon, S.L.*
AU  - Bailiff, I.*
AU  - Bouville, A.*
AU  - Fattibene, P.*
AU  - Kleinerman, R.A.*
AU  - Lloyd, D.C.*
AU  - McKeever, S.W.S.*
AU  - Romanyukha, A.*
AU  - Sevan'kaev, A.V.*
AU  - Tucker, J.D.*
AU  - Wieser, A.
C1  - 2700
C2  - 24981
SP  - 948-971
TI  - BiodosEPR-2006 consensus committee report on biodosimetric methods to evaluate radiation doses at long times after exposure.
JO  - Radiat. Meas.
VL  - 42
IS  - 6-7
PB  - Elsevier
PY  - 2007
SN  - 1350-4487
ER  - 

TY  - JOUR
AB  - The spatial variation of dose rate from a 90Sr/90Y calibration source mounted on a Risø equipment TL-DA-15 was investigated. Six disks accommodating single grains of ?-Al2O3:C were irradiated at the Secondary Standard Dosimetry Laboratory (SSDL) at GSF to a uniform photon radiation field. The corresponding single-grain OSL signals of each grain were then compared with those obtained after the irradiation of the disks with the built-in beta source of the equipment.Additionally, the irradiation system was modelled to perform a Monte Carlo calculation assuming a homogeneous source.A continuous drop of the beta dose rate with increasing radial distance from the centre of the disk was observed in the experiments, indicating that grains located in the central part of the disk absorbed a higher dose than those placed in the outer region of the hole matrix. This experimental dose profile pattern was also confirmed by the results of the Monte Carlo calculation. It can therefore be concluded that different calibration factors, depending on the grain location, should be applied in order to improve the reliability of equivalent dose assessment using single-grain OSL measurements.
AU  - Veronese, I.*
AU  - Shved, V.*
AU  - Shishkina, E.A.*
AU  - Giussani, A.*
AU  - Göksu, H.Y.
C1  - 5812
C2  - 24422
SP  - 138-143
TI  - Study of dose rate profile at sample disks in a Risø OSL single-grain attachment system.
JO  - Radiat. Meas.
VL  - 42
PB  - Elsevier
PY  - 2007
SN  - 1350-4487
ER  - 

TY  - JOUR
AU  - Veronese, I.*
AU  - Giussani, A.*
AU  - Göksu, H.Y.
AU  - Martini, M.*
C1  - 2110
C2  - 21943
SP  - 743-746
TI  - The trap parameters of electrons in intermediate energy levels in quartz.
JO  - Radiat. Meas.
VL  - 38
PY  - 2004
SN  - 1350-4487
ER  - 

TY  - JOUR
AU  - Göksu, H.Y.
AU  - Bailiff, I.K.*
AU  - Mikhailik, V.B.*
C1  - 9901
C2  - 21018
SP  - 323-327
TI  - New approaches to retrospective dosimetry using cementitious building materials. 
JO  - Radiat. Meas.
VL  - 37
PY  - 2003
SN  - 1350-4487
ER  - 

TY  - JOUR
AU  - Göksu, H.Y.
C1  - 9902
C2  - 21143
SP  - 617-620
TI  - Telephone chip-cards as individual dosemeters. 
JO  - Radiat. Meas.
VL  - 37
PY  - 2003
SN  - 1350-4487
ER  - 

TY  - JOUR
AU  - Zdravkova, M.*
AU  - Wieser, A.
AU  - El-Faramawy, N.
AU  - Ivanov, D.*
AU  - Gallez, B.*
AU  - Debyst, R.*
C1  - 9903
C2  - 21415
SP  - 347-353
TI  - An in vitro L-band EPR study whole human teeth in a surface coil resonator. 
JO  - Radiat. Meas.
VL  - 37
PY  - 2003
SN  - 1350-4487
ER  - 

TY  - JOUR
AU  - Kalchgruber, R.*
AU  - Göksu, H.Y.
AU  - Hochhäuser, E.
AU  - Wagner, G.A.*
C1  - 22018
C2  - 20570
SP  - 585-590
TI  - Monitoring environmental dose rate using Riso TL/OSL readers with built-in sources :  recommmendations for users.
JO  - Radiat. Meas.
VL  - 35
PY  - 2002
SN  - 1350-4487
ER  - 

TY  - JOUR
AU  - Göksu, H.Y.
AU  - Schwenk, P.*
AU  - Semioshkina, N.A.
C1  - 21927
C2  - 20266
SP  - 785-792
TI  - Investigation of the thermal stability of 210COD,1,248C TL peak of quartz and dating the components of terrazzo from the monastery church of Tegernsee.
JO  - Radiat. Meas.
VL  - 33
PY  - 2001
SN  - 1350-4487
ER  - 

TY  - JOUR
AU  - Niedermayer, M.
AU  - Göksu, H.Y.
AU  - Dalheimer, A.*
AU  - Bayer, A.*
C1  - 21670
C2  - 19829
SP  - 825-832
TI  - Infrared (IR) stimulated luminescence from modern bricks in retrospective dosimetry applications.
JO  - Radiat. Meas.
VL  - 32
PY  - 2000
SN  - 1350-4487
ER  - 

TY  - JOUR
AU  - Bulur, E.
AU  - Göksu, H.Y.
C1  - 20948
C2  - 19003
SP  - 203-206
TI  - Phototransferred thermoluminescence from alpha-Al2O3:C using blue light emitting diodes.
JO  - Radiat. Meas.
VL  - 30
PY  - 1999
SN  - 1350-4487
ER  - 

TY  - JOUR
AU  - Bulur, E.
AU  - Göksu, H.Y.
C1  - 21153
C2  - 19194
SP  - 505-512
TI  - Infrared (IR) stimulated luminescence from feldspars with linearly increasing excitation light intensity.
JO  - Radiat. Meas.
VL  - 30
PY  - 1999
SN  - 1350-4487
ER  - 

TY  - JOUR
AU  - Bulur, E.
AU  - Göksu, H.Y.
AU  - Wahl, W.
C1  - 20784
C2  - 18833
SP  - 625-638
TI  - Infrared (IR) stimulated luminescence from alpha-AL2O3:C.
JO  - Radiat. Meas.
VL  - 29
PY  - 1998
SN  - 1350-4487
ER  - 

TY  - JOUR
AU  - Bulur, E.
AU  - Göksu, H.Y.
C1  - 20785
C2  - 18834
SP  - 639-650
TI  - OSL from beo ceramics: new observations from an old material.
JO  - Radiat. Meas.
VL  - 29
PY  - 1998
SN  - 1350-4487
ER  -