TY - JOUR AB - A suite of software tools has been developed for dose estimation (BAT, WinFRAT) and prediction of acute health effects (WinFRAT, H-Module) using clinical symptoms and/or changes in blood cell counts. We constructed a database of 191 ARS cases using the METREPOL (n = 167) and the SEARCH-database (n = 24). The cases ranged from unexposed (RC0), to mild (RC1), moderate (RC2), severe (RC3), and lethal ARS (RC4). From 2015-2019, radiobiology students and participants of two NATO meetings predicted clinical outcomes (RC, H-ARS, and hospitalization) based on clinical symptoms. We evaluated the prediction outcomes using the same input datasets with a total of 32 teams and 94 participants. We found that: (1) unexposed (RC0) and mildly exposed individuals (RC1) could not be discriminated; (2) the severity of RC2 and RC3 were systematically overestimated, but almost all lethal cases (RC4) were correctly predicted; (3) introducing a prior education component for non-physicians significantly increased the correct predictions of RC, ARS, and hospitalization by around 10% (p<0.005) with a threefold reduction in variance and a halving of the evaluation time per case; (4) correct outcome prediction was independent of the software tools used; and (5) comparing the dose estimates generated by the teams with H-ARS severity reflected known limitations of dose alone as a surrogate for H-ARS severity. We found inexperienced personnel can use software tools to make accurate diagnostic and treatment recommendations with up to 98% accuracy. Educational training improved the quality of decision making and enabled participants lacking a medical background to perform comparably to experts. AU - Port, M.* AU - Haupt, J.* AU - Ostheim, P.* AU - Majewski, M.* AU - Combs, S.E. AU - Atkinson, M.J. AU - Abend, M.* C1 - 60754 C2 - 49544 CY - Two Commerce Sq, 2001 Market St, Philadelphia, Pa 19103 Usa SP - 400-409 TI - Software tools for the evaluation of clinical signs and symptoms in the medical management of acute radiation syndrome-a five-year experience. JO - Health Phys. VL - 120 IS - 4 PB - Lippincott Williams & Wilkins PY - 2021 SN - 0017-9078 ER - TY - JOUR AB - An international intercomparison was organized by Working Group 7, Internal Dosimetry, of the European Radiation Dosimetry Group in collaboration with Working Group 6, Computational Dosimetry, for measurement and Monte Carlo simulation of Am-241 in three skull phantoms. The main objectives of this combined exercise were (1) comparison of the results of counting efficiency in fixed positions over each head phantom using different germanium detector systems, (2) calculation of the activity of Am-241 in the skulls, (3) comparison of Monte Carlo simulations with measurements (spectrum and counting efficiency), and (4) comparison of phantom performance. This initiative collected knowledge on equipment, detector arrangements, calibration procedures, and phantoms used around the world for in vivo monitoring of Am-241 in exposed persons, as well as on the Monte Carlo skills and tools of participants. Three skull phantoms (BfS, USTUR, and CSR phantoms) were transported from Europe (10 laboratories) to North America (United States and Canada). The BfS skull was fabricated with real human bone artificially labeled with Am-241. The USTUR skull phantom was made from the US Transuranium and Uranium Registries whole-body donor (case 0102) who was contaminated due to an occupational intake of Am-241; one-half of the skull corresponds to real contaminated bone, the other half is real human bone from a noncontaminated person. Finally, the CSR phantom was fabricated as a simple hemisphere of equivalent bone and tissue material. The three phantoms differ in weight, size, and shape, which made them suitable for an efficiency study. Based on their own skull calibration, the participants calculated the activity in the three European Radiation Dosimetry Group head phantoms. The Monte Carlo intercomparison was organized in parallel with the measurement exercise using the voxel representations of the three physical phantoms; there were 16 participants. Three tasks were identified with increasing difficulty: (1) Monte Carlo simulation of the simple CSR hemisphere and the Helmholz Zentrum Munchen high-purity germanium detector for calculating the counting efficiency for the 59.54 keV photons of Am-241, in established measurement geometry; (2) Monte Carlo simulation of particular measurement geometries using the BfS and USTUR voxel phantoms and the Helmholz Zentrum Munchen high-purity germanium detector detector; and (3) application of Monte Carlo methodology to calculate the calibration factor of each participant for the detector system and counting geometry (single or multidetector arrangement) to be used for monitoring a person in each in vivo facility, using complex skull phantoms. The results of both exercises resulted in the conclusion that none of the three available head phantoms is appropriate as a reference phantom for the calibration of germanium detection systems for measuring Am-241 in exposed adult persons. The main reasons for this are: (1) lack of homogeneous activity distribution in the bone material, or (2) inadequate shape/size for simulating an adult skull. Good agreement was found between Monte Carlo results and measurements, which supports Monte Carlo calibration of body counters as an alternative method when appropriate physical phantoms are not available and the detector and source are well known. AU - López, M.A.* AU - Nogueira, P.* AU - Vrba, T.* AU - Tanner, R.J.* AU - Rühm, W. AU - Tolmachev, S.Y.* C1 - 55941 C2 - 46718 CY - Two Commerce Sq, 2001 Market St, Philadelphia, Pa 19103 Usa SP - 193-201 TI - Measurements and Monte Carlo simulations of Am-241 activities in three skull phantoms: EURADOS-USTUR collaboration. JO - Health Phys. VL - 117 IS - 2 PB - Lippincott Williams & Wilkins PY - 2019 SN - 0017-9078 ER - TY - JOUR AB - Exposure of cells to ionizing radiation induces DNA double-strand breaks. To repair double-strand breaks correctly, cells must distinguish between the ends of chromosomes (telomeres) and DNA double-strand breaks within chromosomes. Double-strand breaks in telomeric DNA may lead to telomere shortening and mutagenesis. Eukaryotic cells repair double-strand breaks primarily by two mechanisms: error-free homologous recombination and error-prone nonhomologous end joining, of which homologous recombination is used in early meiotic prophase I to create recombined haploid gametes by two meiotic cell divisions lacking an intervening S-phase. Genotoxic exposures put meiosis at risk to transmit mutations, and ionizing radiation is known to induce large double-strand break-marking phospho (gamma)-H2AX foci along the cores and ends of mouse meiotic chromosomes. However, it remained unclear through which repair pathway the ionizing radiation-induced telomeric double-strand breaks are repaired in late prophase I spermatocytes. Using male wild-type and nonhomologous end joining-deficient (severe combined immunodeficient) mice, this study investigated the kinetics of in vivo double-strand break formation and repair at telomeres of late prophase I chromosomes up to 12 h after 0.5 Gy of whole-body gamma irradiation. Late pachytene and diplotene spermatocytes revealed overlapping gamma-H2AX and telomere repeat signal foci, indicating telomeric DNA damage. The comparison of double-strand break repair rates at telomeres and internal prophase chromosome sites revealed a more rapid double-strand break repair at wild-type telomeres during the first hour after irradiation. Increased double-strand break foci numbers at nonhomologous end joining-deficient telomeres and chromosomes and a slowed repair rate in this DNA-dependent protein kinase catalytic subunit mutant suggest that the fast repair of double-strand breaks in telomeric DNA repeats during late prophase I is largely mediated by canonical nonhomologous end joining. AU - Ahmed, E.A.* AU - Rosemann, M. AU - Scherthan, H.* C1 - 53561 C2 - 44859 SP - 102-107 TI - NHEJ contributes to the fast repair of radiation-induced DNA double-strand breaks at late Prophase I telomeres. JO - Health Phys. VL - 115 IS - 1 PY - 2018 SN - 0017-9078 ER - TY - JOUR AB - In 2015, the Bundeswehr Institute of Radiobiology organized a North Atlantic Treaty Organization exercise to examine the significance of clinical signs and symptoms for the prediction of late-occurring acute radiation syndrome. Cases were generated using either the Medical Treatment Protocols for Radiation Accident Victims (METREPOL, n = 167) system or using real-case descriptions extracted from a database system for evaluation and archiving of radiation accidents based on case histories (SEARCH, n = 24). The cases ranged from unexposed [response category 0 (RC 0, n = 89)] to mild (RC 1, n = 45), moderate (RC 2, n = 19), severe (RC 3, n = 20), and lethal (RC 4, n = 18) acute radiation syndrome. During the previous exercise, expert teams successfully predicted hematological acute radiation syndrome severity, determined whether hospitalization was required, and gave treatment recommendations, taking advantage of different software tools developed by the North Atlantic Treaty Organization teams. The authors provided the same data set to radiobiology students who were introduced to the medical management of acute effects after radiation exposure and the software tools during a class lasting 15 h. Corresponding to the previous results, difficulties in the discrimination between RC 0/RC 1 and RC 3/RC 4, as well as a systematic underestimation of RC 1 and RC 2, were observed. Nevertheless, after merging reported response categories into clinically relevant groups (RC 0-1, RC 2-3, and RC 3-4), it was found that the majority of cases (95.2% ± 2.2 standard deviations) were correctly identified and that 94.7% (±2.6 standard deviations) developing acute radiation syndrome and z96.4% (±1.6 standard deviations) requiring hospitalization were identified correctly. Two out of three student teams also provided a dose estimate. These results are comparable to the best-performing team of the 2015 North Atlantic Treaty Organization exercise (response category: 92.5%; acute radiation syndrome: 95.8%; hospitalization: 96.3%). AU - Majewski, M.* AU - Combs, S.E. AU - Trott, K.* AU - Abend, M.* AU - Port, M.* C1 - 53678 C2 - 44853 SP - 49-56 TI - Successful teaching of radiobiology students in the medical management of acute radiation effects from real case histories using clinical signs and symptoms and taking advantage of recently developed software tools. JO - Health Phys. VL - 115 IS - 1 PY - 2018 SN - 0017-9078 ER - TY - JOUR AB - The National Council on Radiation Protection and Measurements (NCRP) established NCRP Scientific Committee 2-6 to develop a report on the current state of knowledge and guidance for radiation safety programs involved with nanotechnology. Nanotechnology is the understanding and control of matter at the nanoscale, at dimensions between ∼1 and 100 nm, where unique phenomena enable novel applications. While the full report is in preparation, this paper presents and applies an informatics-based decision-making framework and process through which the radiation protection community can anticipate that nano-enabled applications, processes, nanomaterials, and nanoparticles are likely to become present or are already present in radiation-related activities; recognize specific situations where environmental and worker safety, health, well-being, and productivity may be affected by nano-related activities; evaluate how radiation protection practices may need to be altered to improve protection; control information, interpretations, assumptions, and conclusions to implement scientifically sound decisions and actions; and confirm that desired protection outcomes have been achieved. This generally applicable framework and supporting process can be continuously applied to achieve health and safety at the convergence of nanotechnology and radiation-related activities. AU - Hoover, M.D.* AU - Myers, D.S.* AU - Cash, L.J.* AU - Guilmette, R.A.* AU - Kreyling, W.G. AU - Oberdörster, G.* AU - Smith, R.* AU - Cassata, J.R.* AU - Boecker, B.B.* AU - Grissom, M.P.* C1 - 43024 C2 - 36006 SP - 179-194 TI - Application of an informatics-based decision-making framework and process to the assessment of radiation safety in nanotechnology. JO - Health Phys. VL - 108 IS - 2 PY - 2015 SN - 0017-9078 ER - TY - JOUR AB - Groups of Japanese and American scientists, supported by international collaborators, have worked for many years to ensure the accuracy of the radiation dosimetry used in studies of health effects in the Japanese atomic bomb survivors. Reliable dosimetric models and systems are especially critical to epidemiologic studies of this population because of their importance in the development of worldwide radiation protection standards. While dosimetry systems, such as Dosimetry System 1986 (DS86) and Dosimetry System 2002 (DS02), have improved, the research groups that developed them were unable to propose or confirm an additional contribution by residual radiation to the survivor's total body dose. In recognition of the need for an up-to-date review of residual radiation exposures in Hiroshima and Nagasaki, a half-day technical session was held for reports on newer studies at the 59th Annual HPS Meeting in 2014 in Baltimore, MD. A day-and-a-half workshop was also held to provide time for detailed discussion of the newer studies and to evaluate their potential use in clarifying the residual radiation exposure to atomic bomb survivors at Hiroshima and Nagasaki. The process also involved a re-examination of very early surveys of radioisotope emissions from ground surfaces at Hiroshima and Nagasaki and early reports of health effects. New insights were reported on the potential contribution to residual radiation from neutron-activated radionuclides in the airburst's dust stem and pedestal and in unlofted soil, as well as from fission products and weapon debris from the nuclear cloud. However, disparate views remain concerning the actual residual radiation doses received by the atomic bomb survivors at different distances from the hypocenter. The workshop discussion indicated that measurements made using thermal luminescence and optically stimulated luminescence, like earlier measurements, especially in very thin layers of the samples, could be expanded to detect possible radiation exposures to beta particles and to determine their significance plus the extent of the various residual radiation areas at Hiroshima and Nagasaki. Other suggestions for future residual radiation studies are included in this workshop report. AU - Kerr, G.D.* AU - Egbert, S.D.* AU - Al-Nabulsi, I.* AU - Bailiff, I.K.* AU - Beck, H.L.* AU - Belukha, I.G.* AU - Cockayne, J.E.* AU - Cullings, H.M.* AU - Eckerman, K.F.* AU - Granovskaya, E.* AU - Grant, E.J.* AU - Hoshi, M.* AU - Kaul, D.C.* AU - Kryuchkov, V.* AU - Mannis, D.* AU - Ohtaki, M.* AU - Otani, K.* AU - Shinkarev, S.* AU - Simon, S.L.* AU - Spriggs, G.D.* AU - Stepanenko, V.F.* AU - Stricklin, D.* AU - Weiss, J.F.* AU - Weitz, R.L.* AU - Woda, C. AU - Worthington, P.R.* AU - Yamamoto, K.* AU - Young, R.W.* C1 - 47231 C2 - 39279 SP - 582-600 TI - Workshop report on atomic bomb dosimetry: Review of dose related factors for the evaluation of exposures to residual radiation at Hiroshima and Nagasaki. JO - Health Phys. VL - 109 IS - 6 PY - 2015 SN - 0017-9078 ER - TY - JOUR AB - Skull counting can be used to assess the activity of radionuclides internally deposited in the bone. The Human Monitoring Laboratory (HML) at Health Canada conducted the measurement of Am in the BfS (Bundesamt für Strahlenschuts) skull phantom on contact with the skull for various positions. By placing the detector in contact, the HML can improve the counting efficiency by over 20% compared to placing the detector 1 cm above the surface of the skull. Among all the positions tested, the forehead position is the preferred counting geometry due to the design of HML's counting facility and the comfort it would provide to the individual being counted, although this counting position did not offer the highest counting efficiency for the gamma rays (either the 59.5 keV or the 26.3 keV) emitted by Am. AU - Li, C.* AU - Hauck, B.* AU - Capello, K.* AU - Nogueira, P. AU - Lopez, M.A.* AU - Kramer, G.H.* C1 - 43189 C2 - 36308 CY - Philadelphia SP - 380-382 TI - Counting 241Am in the BfS human skull phantom on contact - evaluation in the human monitoring laboratory. JO - Health Phys. VL - 108 IS - 3 PB - Lippincott Williams & Wilkins PY - 2015 SN - 0017-9078 ER - TY - JOUR AB - The authors evaluated gene expression in the peripheral blood in relation to occupational exposure in Mayak workers to find out about the existence of a permanent post exposure signature. Workers were exposed to combined incorporated Pu and external gamma rays (n = 82) or to external gamma rays only (n = 18), and 50 unexposed individuals served as controls. Peripheral blood was taken from workers older than 70 y. RNA was isolated, converted into cDNA, and stored at -20°C. A two-stage study design was performed focusing on examinations on the transcriptional (mRNA) and post-transcriptional level (microRNA). In the first stage, 40 samples were identified for screening purposes and selection of candidate genes. For examinations on the transcriptional level, whole genome microarrays and qRT-PCR were employed on the post-transcriptional level (667 microRNAs). Candidate genes were assessed by (1) introducing a twofold difference in gene expression over the reference group and (2) showing a significant p-value using the Kruskal-Wallis test. From 42,545 transcripts of the whole genome microarray, 376 candidate genes (80 up-regulated and 296 down-regulated relative to the reference group) were selected. Expression of almost all of these genes (70-98%) appeared significantly associated with internal Pu and to a lesser extent were associated with external gamma-ray exposure (2-30%). Associations in the same direction were found for 45 microRNAs. Although both exposures led to modulations of different gene sets in different directions, the authors could detect no differences in gene set enrichment analysis. AU - Abend, M.* AU - Azizova, T.V.* AU - Müller, K.* AU - Dörr, H.* AU - Senf, S.* AU - Kreppel, H.* AU - Rusinova, G.* AU - Glazkova, I.* AU - Vyazovskaya, N.* AU - Schmidl, D. AU - Unger, K. AU - Meineke, V.* C1 - 31174 C2 - 34217 SP - 664-676 TI - Gene expression analysis in Mayak workers with prolonged occupational radiation exposure. JO - Health Phys. VL - 106 IS - 6 PY - 2014 SN - 0017-9078 ER - TY - JOUR AB - In this note, the authors describe the MULTIBIODOSE software, which has been created as part of the MULTIBIODOSE project. The software enables doses estimated by networks of laboratories, using up to five retrospective (biological and physical) assays, to be combined to give a single estimate of triage category for each individual potentially exposed to ionizing radiation in a large scale radiation accident or incident. The MULTIBIODOSE software has been created in Java. The usage of the software is based on the MULTIBIODOSE Guidance: the program creates a link to a single SQLite database for each incident, and the database is administered by the lead laboratory. The software has been tested with Java runtime environment 6 and 7 on a number of different Windows, Mac, and Linux systems, using data from a recent intercomparison exercise. The Java program MULTIBIODOSE_1.0.jar is freely available to download from http://www.multibiodose.eu/software or by contacting the software administrator: MULTIBIODOSE-software@gmx.com. AU - Ainsbury, E.A.* AU - Barnard, S.* AU - Barrios, L.* AU - Fattibene, P.* AU - de Gelder, V.* AU - Gregoire, E.* AU - Lindholm, C.* AU - Lloyd, D.* AU - Nergaard, I.* AU - Rothkamm, K.* AU - Romm, H.* AU - Scherthan, H.* AU - Thierens, H.* AU - Vandevoorde, C.* AU - Woda, C. AU - Wojcik, A.* C1 - 31364 C2 - 34505 CY - Philadelphia SP - 83-89 TI - Multibiodose radiation emergency triage categorization software. JO - Health Phys. VL - 107 IS - 1 PB - Lippincott Williams & Wilkins PY - 2014 SN - 0017-9078 ER - TY - JOUR AB - There is a need for accurate dosimetry for studies of health effects in the Japanese atomic bomb survivors because of the important role that these studies play in worldwide radiation protection standards. International experts have developed dosimetry systems, such as the Dosimetry System 2002 (DS02), which assess the initial radiation exposure to gamma rays and neutrons but only briefly consider the possibility of some minimal contribution to the total body dose by residual radiation exposure. In recognition of the need for an up-to-date review of the topic of residual radiation exposure in Hiroshima and Nagasaki, recently reported studies were reviewed at a technical session at the 57th Annual Meeting of the Health Physics Society in Sacramento, California, 22-26 July 2012. A one-day workshop was also held to provide time for detailed discussion of these newer studies and to evaluate their potential use in clarifying the residual radiation exposures to the atomic-bomb survivors at Hiroshima and Nagasaki. Suggestions for possible future studies are also included in this workshop report. AU - Kerr, G.D.* AU - Egbert, S.D.* AU - Al-Nabulsi, I.* AU - Beck, H.L.* AU - Cullings, H.M.* AU - Endo, S.* AU - Hoshi, M.* AU - Imanaka, T.* AU - Kaul, D.C.* AU - Maruyama, S.* AU - Reeves, G.I.* AU - Rühm, W. AU - Sakaguchi, A.* AU - Simon, S.L.* AU - Spriggs, G.D.* AU - Stram, D.O.* AU - Tonda, T.* AU - Weiss, J.F.* AU - Weitz, R.L.* AU - Young, R.W.* C1 - 26025 C2 - 32028 CY - Philadelphia SP - 140-149 TI - Workshop report on atomic bomb dosimetry-RESIDUAL radiation exposure: Recent research and suggestions for future studies. JO - Health Phys. VL - 105 IS - 2 PB - Lippincott Williams & Wilkins PY - 2013 SN - 0017-9078 ER - TY - JOUR AB - no Abstract AU - Kramer, G.H.* AU - López, M.A.* AU - Broggio, D.* AU - Tolmachev, S.* AU - Rühm, W. C1 - 7236 C2 - 29600 SP - 354-355 TI - Natural vs. artificial anthropometric phantoms for measuring bone-seeking radionuclides. Reply to Spitz et al. JO - Health Phys. VL - 102 IS - 3 PB - Lippincott Williams&Wilkins PY - 2012 SN - 0017-9078 ER - TY - JOUR AB - Three facilities (CIEMAT, HMGU and HML) have used their in vivo counters to compare two leg phantoms. One was commercially produced with (241)Am activity artificially added to the bone inserts. The other, the United States Transuranium and Uranium Registries' (USTUR) leg phantom, was manufactured from (241)Am-contaminated bones resulting from an intake. The comparison of the two types of leg phantoms showed that the two phantoms are not similar in their activity distributions. An error in a bone activity estimate could be quite large if the commercial leg phantom is used to estimate what is contained in the USTUR leg phantom and, consequently, a real person. As the latter phantom was created as a result of a real contamination, it is deemed to be the more representative of what would actually happen if a person were internally contaminated with (241)Am. AU - Kramer, G.H.* AU - Hauck, B.* AU - Capello, K.* AU - Rühm, W. AU - El-Faramawy, N.* AU - Broggio, D.* AU - Franck, D.* AU - López, M.A.* AU - Navarro, T.* AU - Navarro, J.F.* AU - Perez, B.* AU - Tolmachev, S.* C1 - 3763 C2 - 28927 SP - 248-258 TI - Comparison of two leg phantoms containing 241Am in bone. JO - Health Phys. VL - 101 IS - 3 PB - Lippincott Williams &Wilkins PY - 2011 SN - 0017-9078 ER - TY - JOUR AB - The reliability of biokinetic models is essential for the assessment of internal doses and a radiation risk analysis for the public and occupational workers exposed to radionuclides. In the present study, a method for assessing the reliability of biokinetic models by means of uncertainty and sensitivity analysis was developed. In the first part of the paper, the parameter uncertainty was analyzed for two biokinetic models of zirconium (Zr); one was reported by the International Commission on Radiological Protection (ICRP), and one was developed at the Helmholtz Zentrum München-German Research Center for Environmental Health (HMGU). In the second part of the paper, the parameter uncertainties and distributions of the Zr biokinetic models evaluated in Part I are used as the model inputs for identifying the most influential parameters in the models. Furthermore, the most influential model parameter on the integral of the radioactivity of Zr over 50 y in source organs after ingestion was identified. The results of the systemic HMGU Zr model showed that over the first 10 d, the parameters of transfer rates between blood and other soft tissues have the largest influence on the content of Zr in the blood and the daily urinary excretion; however, after day 1,000, the transfer rate from bone to blood becomes dominant. For the retention in bone, the transfer rate from blood to bone surfaces has the most influence out to the endpoint of the simulation; the transfer rate from blood to the upper larger intestine contributes a lot in the later days; i.e., after day 300. The alimentary tract absorption factor (fA) influences mostly the integral of radioactivity of Zr in most source organs after ingestion. AU - Li, W.B. AU - Greiter, M. AU - Oeh, U. AU - Hoeschen, C. C1 - 6737 C2 - 29191 SP - 677-692 TI - Reliability of a new biokinetic model of zirconium in internal dosimetry: Part II, parameter sensitivity analysis. JO - Health Phys. VL - 101 IS - 6 PB - Lippincott Williams&Wilkins PY - 2011 SN - 0017-9078 ER - TY - JOUR AB - The reliability of biokinetic models is essential in internal dose assessments and radiation risk analysis for the public, occupational workers, and patients exposed to radionuclides. In this paper, a method for assessing the reliability of biokinetic models by means of uncertainty and sensitivity analysis was developed. The paper is divided into two parts. In the first part of the study published here, the uncertainty sources of the model parameters for zirconium (Zr), developed by the International Commission on Radiological Protection (ICRP), were identified and analyzed. Furthermore, the uncertainty of the biokinetic experimental measurement performed at the Helmholtz Zentrum München-German Research Center for Environmental Health (HMGU) for developing a new biokinetic model of Zr was analyzed according to the Guide to the Expression of Uncertainty in Measurement, published by the International Organization for Standardization. The confidence interval and distribution of model parameters of the ICRP and HMGU Zr biokinetic models were evaluated. As a result of computer biokinetic modelings, the mean, standard uncertainty, and confidence interval of model prediction calculated based on the model parameter uncertainty were presented and compared to the plasma clearance and urinary excretion measured after intravenous administration. It was shown that for the most important compartment, the plasma, the uncertainty evaluated for the HMGU model was much smaller than that for the ICRP model; that phenomenon was observed for other organs and tissues as well. The uncertainty of the integral of the radioactivity of Zr up to 50 y calculated by the HMGU model after ingestion by adult members of the public was shown to be smaller by a factor of two than that of the ICRP model. It was also shown that the distribution type of the model parameter strongly influences the model prediction, and the correlation of the model input parameters affects the model prediction to a certain extent depending on the strength of the correlation. In the case of model prediction, the qualitative comparison of the model predictions with the measured plasma and urinary data showed the HMGU model to be more reliable than the ICRP model; quantitatively, the uncertainty model prediction by the HMGU systemic biokinetic model is smaller than that of the ICRP model. The uncertainty information on the model parameters analyzed in this study was used in the second part of the paper regarding a sensitivity analysis of the Zr biokinetic models. AU - Li, W.B. AU - Greiter, M. AU - Oeh, U. AU - Hoeschen, C. C1 - 6738 C2 - 29193 SP - 660-676 TI - Reliability of a new biokinetic model of zirconium in internal dosimetry: Part I, parameter uncertainty analysis. JO - Health Phys. VL - 101 IS - 6 PB - Lippincott Williams&Wilkins PY - 2011 SN - 0017-9078 ER - TY - JOUR AB - The dicentric assay was established to carry out cytogenetic biodosimetry after suspected radiation overexposure, including a comprehensive documentation system to record the processing of the specimen, all data, results, and stored information. As an essential prerequisite for retrospective radiation dose assessment, a dose-response curve for dicentric induction by in vitro x-ray irradiation of peripheral blood samples was produced. The accelerating potential was 240 kV (maximum photon energy: 240 keV). A total of 8,377 first-division metaphases of four healthy volunteers were analyzed after exposure to doses ranging from 0.2 to 4.0 Gy at a dose rate of 1.0 Gy min. The background level of aberrations at 0-dose was determined by the analysis of 14,522 first-division metaphases obtained from unirradiated blood samples of 10 healthy volunteers. The dose-response relationship follows a linear-quadratic equation, Y = c + alphaD + betaD, with the coefficients c = 0.0005 +/- 0.0002, alpha = 0.043 +/- 0.006, and beta = 0.063 +/- 0.004. The technical competence and the quality of the calibration curve were assessed by determination of the dose prediction accuracy in an in vitro experiment simulating whole-body exposures within a range of 0.2 to 2.0 Gy. Dose estimations were derived by scoring up to 500-1,000 metaphase spreads or more (full estimation mode) and by evaluating only 50 metaphase spreads (triage mode) per subject. The triage mode was applied by performing manifold evaluations of the full estimation data in order to test the robustness of the curve for triage purposes and to assess possible variations among the estimated doses referring to a single exposure and preparation. AU - Beinke, C.* AU - Braselmann, H. AU - Meineke, V.* C1 - 2093 C2 - 28081 SP - 261-268 TI - Establishment of an X-ray standard calibration curve by conventional dicentric analysis as prerequisite for accurate radiation dose assessment. JO - Health Phys. VL - 98 IS - 2 PB - Lippincott Williams & Wilkins PY - 2010 SN - 0017-9078 ER - TY - JOUR AB - Diethylene Triamine Pentaacetic Acid (DTPA) is used for decorporation of plutonium because it is known to be able to enhance its urinary excretion for several days after treatment by forming stable Pu-DTPA complexes. The decorporation prevents accumulation in organs and results in a dosimetric benefit, which is difficult to quantify from bioassay data using existing models. The development of a biokinetic model describing the mechanisms of actinide decorporation by administration of DTPA was initiated as a task in the European COordinated Network on RAdiation Dosimetry (CONRAD). The systemic biokinetic model from Leggett et al. and the biokinetic model for DTPA compounds of International Commission on Radiological Protection Publication 53 were the starting points. A new model for biokinetics of administered DTPA based on physiological interpretation of 14C-labeled DTPA studies from literature was proposed by the group. Plutonium and DTPA biokinetics were modeled separately. The systems were connected by means of a second order kinetics process describing the chelation process of plutonium atoms and DTPA molecules to Pu-DTPA complexes. It was assumed that chelation only occurs in the blood and in systemic compartment ST0 (representing rapid turnover soft tissues), and that Pu-DTPA complexes and administered forms of DTPA share the same biokinetic behavior. First applications of the CONRAD approach showed that the enhancement of plutonium urinary excretion after administration of DTPA was strongly influenced by the chelation rate constant. Setting it to a high value resulted in a good fit to the observed data. However, the model was not yet satisfactory since the effects of repeated DTPA administration in a short time period cannot be predicted in a realistic way. In order to introduce more physiological knowledge into the model several questions still have to be answered. Further detailed studies of human contamination cases and experimental data will be needed in order to address these issues. The work is now continued within the European Radiation Dosimetry Group, EURADOS. AU - Breustedt, B.* AU - Blanchardon, E.* AU - Berard, P.* AU - Fritsch, P.* AU - Giussani, A. AU - López, M.A.* AU - Luciani, A.* AU - Nosske, D.* AU - Piechowski, J.* AU - Schimmelpfeng, J.* AU - Sérandour, A.L.* C1 - 2000 C2 - 27511 SP - 547-552 TI - The CONRAD approach to biokinetic modeling of DTPA decorporation therapy. JO - Health Phys. VL - 99 IS - 4 PB - Lippincott Williams & Wilkins PY - 2010 SN - 0017-9078 ER - TY - JOUR AB - This note discusses the significant impact on effective doses received during commercial flights calculated using the new International Commission on Radiological Protection (ICRP) radiation weighting factors. It also provides an update on adult effective doses given in a previous article in Health Physics when the old ICRP radiation weighting factors were used. AU - Chen, J.* AU - Mares, V. C1 - 6067 C2 - 27816 SP - 74-76 TI - Significant impact on effective doses received during commercial flights calculated using the new ICRP radiation weighting factors. JO - Health Phys. VL - 98 IS - 1 PB - Lippincott Williams & Wilkins PY - 2010 SN - 0017-9078 ER - TY - JOUR AB - The current dose coefficients for internal dose assessment of occupationally exposed persons and the general public were derived using the methodology of the International Commission on Radiological Protection (ICRP), which is similar to the Medical Internal Radiation Dose (MIRD)-type methodology. One component of this methodology is the mathematical representation of the human body (so-called MIRD-type phantoms) developed at the Oak Ridge National Laboratory for calculations of photon specific absorbed fractions (SAFs). Concerning the beta emissions, it is assumed in general that they irradiate only the organ where the radionuclide resides, whereas for walled organs, a fixed fraction of the emitted energy is absorbed within the wall. For the active marrow and bone surface targets, absorbed fractions were explicitly provided in ICRP Publication 30. The ICRP Publications 66 and 100 contain further detailed energy-dependent absorbed fraction data for the airways and the segments of the alimentary tract. In the present work, the voxel phantoms representing the reference male and female adults, recently developed at the Helmholtz Zentrum München-German Research Center for Environmental Health (HMGU) in collaboration with the Task Group DOCAL of ICRP Committee 2, were used for the Monte Carlo computation of photon as well as electron SAFs. These voxel phantoms, being constructed from computed tomography (CT) scans of individuals, are more realistic in shape and location of organs in the body than the mathematical phantoms; therefore, they provide photon SAFs that are more precise than those stemming from mathematical phantoms. In addition, electron SAFs for solid and walled organs as well as tissues in the alimentary tract, the respiratory tract, and the skeleton were calculated with Monte Carlo methods using these phantoms to complement the data of ICRP Publications 66 and 100 that are confined to self-irradiation. The SAFs derived for photons and electrons are then used to calculate the dose coefficients of the beta emitters 141Ce, 144Ce, 95Zr, and 90Sr. It is found that the differences of the dose coefficients due to the revised SAFs are much larger for injection and ingestion than for inhalation. The equivalent doses for colon and ingestion with the new voxel-based SAFs are significantly smaller than the values with the MIRD-type photon SAFs and simplifying assumptions for electrons. For lungs and inhalation, no significant difference was observed for the equivalent doses, whereas for injection and ingestion, an increase of the new values is observed. AU - Li, W.B. AU - Zankl, M. AU - Schlattl, H. AU - Petoussi-Henß, N. AU - Eckerman, K.F.* AU - Bolch, W.E.* AU - Oeh, U. AU - Hoeschen, C. C1 - 5684 C2 - 27399 SP - 503-510 TI - Impact on ¹⁴¹Ce, ¹⁴⁴Ce, ⁹⁵Zr, and ⁹⁰Sr beta emitter dose coefficients of photon and electron SAFs calculated with ICRP/ICRU reference adult voxel computational phantoms. JO - Health Phys. VL - 99 IS - 4 PB - Health Physics Society PY - 2010 SN - 0017-9078 ER - TY - JOUR AB - To predict uranium in human hair due to chronic exposure through drinking water, a compartment representing human hair was added into the uranium biokinetic model developed by the International Commission on Radiological Protection (ICRP). The hair compartmental model was used to predict uranium excretion in human hair as a bioassay indicator due to elevated uranium intakes. Two excretion pathways, one starting from the compartment of plasma and the other from the compartment of intermediate turnover soft tissue, are assumed to transfer uranium to the compartment of hair. The transfer rate was determined from reported uranium contents in urine and in hair, taking into account the hair growth rate of 0.1 g d(-1). The fractional absorption in the gastrointestinal tract of 0.6% was found to fit best to describe the measured uranium levels among the users of drilled wells in Finland. The ingestion dose coefficient for U-238, which includes its progeny of Th-234, Pa-234, and Pa-234, was calculated equal to 1.3 X 10(-8) Sv Bq(-1) according to the hair compartmental model. This estimate is smaller than the value of 4.5 X 10(-8) Sv Bq(-1) published by ICRP for the members of the public. In this new model, excretion of uranium through urine is better represented when excretion to the hair compartment is accounted for and hair analysis can provide a means for assessing the internal body burden of uranium. The model is applicable for chronic exposure as well as for an acute exposure incident. In the latter case, the hair sample can be collected and analyzed even several days after the incident, whereas urinalysis requires sample collection shortly after the exposure. The model developed in this study applies to ingestion intakes of uranium. AU - Li, W.B. AU - Karpas, Z.* AU - Salonen, L.* AU - Kurttio, P.* AU - Muikku, M.* AU - Wahl, W. AU - Höllriegl, V. AU - Hoeschen, C. AU - Oeh, U. C1 - 1655 C2 - 26176 SP - 636-645 TI - A compartmental model of uranium in human hair for protracted ingestion of natural uranium in drinking water. JO - Health Phys. VL - 96 IS - 6 PB - Lippincott Williams & Wilkins PY - 2009 SN - 0017-9078 ER - TY - JOUR AB - This study assesses the radiation exposure from cosmic rays to fetuses of pregnant aircrew and air travelers. Combining the particle fluence spectra of various cosmic radiations at aircraft altitudes with the fetal fluence-to-dose conversion coefficients calculated for different cosmic ray radiations, the doses to the fetal body were estimated for three prenatal ages. From the five major particle types present during commercial flights, neutrons contribute about 54% of the total fetal dose, followed by protons 22%, photons 11%, electrons 7%, and muons 6%. The results indicate that the dose to the fetus can exceed a recommended fetal dose limit of 1 mSv after 10 round trips on commercial flights between Toronto and Frankfurt. AU - Chen, J.* AU - Mares, V. C1 - 3071 C2 - 28278 SP - 407-412 TI - Estimate of doses to the fetus during commercial flights. JO - Health Phys. VL - 95 IS - 4 PB - Lippincott Williams&Wilkins PY - 2008 SN - 0017-9078 ER - TY - JOUR AB - Studies on miners as well as epidemiological studies in the general population show an increased lung cancer risk after exposure to radon and its progeny. The European pooled analysis of indoor radon studies estimates an excess relative risk of 8% (16% after correction for measurement uncertainties) per 100 Bq m(-3) indoor radon concentration. Here, we determine the population attributable fraction (PAF) for lung cancer due to residential radon based on this risk estimate for Switzerland and Germany. Based on regionally stratified radon data, the PAF was calculated following the World Health Organization concept of global burden of disease, compared to a realistic baseline radon concentration equal to the outdoor concentration. Lifetable approaches were used taking smoking and sex into account. Measurement error corrections were applied to both risk estimates and the radon distribution. In Switzerland, the average indoor radon concentration is 78 Bq m(-3), resulting in a PAF of 8.3%. Therefore, 169 male lung cancer deaths and 62 deaths in women can be attributed to residential radon per year. For Germany, the average indoor radon concentration is 49 Bq m(-3), corresponding to a PAF of 5.0% (1,422 male and 474 female deaths annually). In both countries, a large regional variation in the PAF was observed due to regional differences in radon concentrations and population structure. Both calculations show a strong dependency on the risk model used. Risk models based on miner studies result in higher PAF estimates than risk models based on indoor radon studies due to different assumptions regarding exposures received more than 35 years ago. The use of a non-zero baseline radon concentration also contributes to the lower PAF estimates reported here. Although the estimates of the population attributable fraction of residential radon presented here are lower than previously reported estimates, the risk is still one of the most widespread environmental hazards. Radon monitoring and radon reduction programs are therefore important issues for environmental public health management. AU - Menzler, S.* AU - Piller, G.* AU - Gruson, M.* AU - Schaffrath-Rosario, A. AU - Wichmann, H.-E. AU - Kreienbrock, L.* C1 - 403 C2 - 25562 SP - 179-189 TI - Population attributable fraction for lung cancer due to residential radon in Switzerland and Germany. JO - Health Phys. VL - 95 IS - 2 PB - Lippincott, Williams & Wilkins PY - 2008 SN - 0017-9078 ER - TY - JOUR AB - For about one decade, activation measurements performed on environmental samples from a distance larger than 1 km from the hypocenter of the atomic-bomb explosion over Hiroshima suggested much higher thermal neutron fluences to the survivors than predicted. This caused concern among the radiation protection community and prompted a complete re-evaluation of all aspects of survivor dosimetry. While it was shown recently that secondary neutrons from cosmic radiation and other sources have probably been the reason for the high measured concentrations of the long-lived radioisotope 36Cl in these samples, the source for high measured concentrations of the short-lived radionuclides 152Eu and 60Co has not yet been investigated in detail. In order to quantify the production of 152Eu and 60Co in environmental samples by secondary neutrons from cosmic radiation, thermal neutron fluxes were measured by means of a He gas proportional counter in various buildings where these samples had been and still are being stored. Because a 252Cf neutron source has been operated occasionally close to one of the sample storage rooms, additional neutron flux measurements were carried out when the neutron source was in operation. The thermal neutron fluxes measured ranged from 0.00017 to 0.00093 n cm(-2) s(-1) and depended on the floor number of the investigated building. Based on the measured neutron fluxes, the specific activities from the reactions 151Eu(n,gamma)152Eu and 59Co(n,gamma)60Co in the atomic-bomb samples were estimated to be 7.9 mBq g(-1) Eu and 0.27 mBq g(-1) Co, respectively, in saturation. These activities are much lower than those recently measured in samples that had been exposed to atomic-bomb neutrons. It is therefore concluded that environmental and moderated 252Cf neutrons are not the source for the high activities that had been measured in these samples. AU - Endo, S.* AU - Shizuma, K.* AU - Tanaka, K.* AU - Ishikawa, M.* AU - Rühm, W. AU - Egbert, S.D.* AU - Hoshi, M.* C1 - 4251 C2 - 24886 SP - 689-695 TI - Radioactivity in atomic-bomb samples from exposure to environmental neutrons. JO - Health Phys. VL - 93 IS - 6 PB - Lippincott Williams & Wilkins PY - 2007 SN - 0017-9078 ER - TY - JOUR AB - In order to resolve the discrepancy between the measured and calculated 152Eu activity induced by the atomic bomb at Hiroshima, extremely low background gamma-ray spectrometry was performed for 17 granite samples collected from 134 m to more than 3 km from the hypocenter. Measurements agreed well with theoretical calculations based on DS02 up to 1.4 km from hypocenter. AU - Komura, K.* AU - Hoshi, M* AU - Endo, S.* AU - Imanaka, T.* AU - Egbert, S.D.* AU - Rühm, W. AU - Fukushima, H.* AU - Fujita, S.* C1 - 2061 C2 - 24633 SP - 366-370 TI - Atomic bomb induced 152Eu: Reconciliation of discrepancy between measurements and calculation. JO - Health Phys. VL - 92 IS - 4 PB - Lippincott Williams & Wilkins PY - 2007 SN - 0017-9078 ER - TY - JOUR AU - Brüske, I. AU - Schaffrath Rosario, A. AU - Wölke, G. AU - Heinrich, J. AU - Kreuzer, M.* AU - Kreienbrock, L.* AU - Wichmann, H.-E. C1 - 4243 C2 - 23681 SP - 208-216 TI - Lung cancer risk among former uranium miners of the Wismut company in Germany. JO - Health Phys. VL - 90 PY - 2006 SN - 0017-9078 ER - TY - JOUR AU - Höllriegl, V. AU - Li, W.B. AU - Oeh, U. AU - Roth, P. C1 - 3061 C2 - 23512 SP - 232-240 TI - Methods for assessing gastrointestinal absorption of strontium in humans by stable tracer techniques. JO - Health Phys. VL - 90 PY - 2006 SN - 0017-9078 ER - TY - JOUR AU - Kellerer, A.M. AU - Rühm, W. AU - Walsh, L.* C1 - 4511 C2 - 23970 SP - 554-564 TI - Indications of the neutron effect contribution in the solid cancer data of the A-bomb survivors. JO - Health Phys. VL - 90 PY - 2006 SN - 0017-9078 ER - TY - JOUR AU - Li, W.B. AU - Salonen, L.* AU - Muikku, M.* AU - Wahl, W. AU - Höllriegl, V. AU - Oeh, U. AU - Roth, P. AU - Rahola, T.* C1 - 3278 C2 - 23567 SP - 533-543 TI - Internal dose assessment of natural uranium from drinking water based of biokinetic modeling and individual bioassay monitoring : a study of a Finnish family. JO - Health Phys. VL - 90 PY - 2006 SN - 0017-9078 ER - TY - JOUR AU - Ramzaev, V.* AU - Göksu, H.Y. C1 - 4927 C2 - 23730 SP - 263-269 TI - Cumulative dose assessment using thermoluminescence properties of porcelan isolators as evidence of a severe radiation accident in the Republic of Sakha (Yakutia), Russia. JO - Health Phys. VL - 91 PY - 2006 SN - 0017-9078 ER - TY - JOUR AU - Bailiff, I.K.* AU - Göksu, H.Y. AU - Meckbach, R. C1 - 4811 C2 - 22911 SP - 233-246 TI - Retrospective luminescence dosimetry : Development of approaches to application in populated areas downwind of the Chernobyl NPP. JO - Health Phys. VL - 89 PY - 2005 SN - 0017-9078 ER - TY - JOUR AU - Degteva, M.O.* AU - Anspaugh, L.R.* AU - Akleyev, A.V.* AU - Jacob, P. AU - Ivanov, D.V.* AU - Wieser, A. AU - Vorobiova, M.I.* AU - Shishkina, E.A.* AU - Shved, V.A.* AU - Vozilova, A.* AU - Bayankin, S.N.* C1 - 1585 C2 - 22477 SP - 139-153 TI - Electron paramagnetic resonance and fluorescence in situ hybridization-based investigations of individual doses for persons living at Metlino in the upper reaches of the Techa River. JO - Health Phys. VL - 88 PY - 2005 SN - 0017-9078 ER - TY - JOUR AU - Roth, P. AU - Höllriegl, V. AU - Li, W.B. AU - Oeh, U. AU - Schramel, P. C1 - 3218 C2 - 22640 SP - 223-228 TI - Validating an important aspect of the new ICRP biokinetic model of thorium. JO - Health Phys. VL - 88 PY - 2005 SN - 0017-9078 ER - TY - JOUR AU - Ulanowski, A. AU - Wieser, A. AU - Zankl, M. AU - Jacob, P. C1 - 1998 C2 - 23398 SP - 645-659 TI - Photon dose conversion coefficients for human teeth in standars irradiation geometries. JO - Health Phys. VL - 89 PY - 2005 SN - 0017-9078 ER - TY - JOUR AU - Wichmann, H.-E. AU - Schaffrath Rosario, A. AU - Heid, I.M. AU - Kreuzer, M.* AU - Heinrich, J. AU - Kreienbrock, L.* C1 - 4548 C2 - 22620 SP - 71-79 TI - Increased lung cancer risk due to residential radon in a pooled and extended analysis of studies in Germany. JO - Health Phys. VL - 88 PY - 2005 SN - 0017-9078 ER - TY - JOUR AU - Bailiff, I.K.* AU - Stepanenko, V.F.* AU - Göksu, H.Y. AU - Jungner, H.* AU - Balmukjanov, S.B.* AU - Balmukhanov, T.S.* AU - Khamidova, L.G.* AU - Kisilev, V.I.* AU - Kolyado, I.B.* AU - Kolizshenkov, T.V.* AU - Shoikhet, Y.N.* C1 - 3391 C2 - 22258 SP - 625-641 TI - The application of retrospective luminescence dosimetry in areas affected by fallout from the semipalatinsk nuclear test site: An evaluation of potential. JO - Health Phys. VL - 87 PY - 2004 SN - 0017-9078 ER - TY - JOUR AB - The cumulative absorbed dose in bricks collected from six buildings in two heavily contaminated settlements (137Cs > 2,000 kBq m(-2)) located downwind of the Chernobyl Nuclear Power Plant was determined using luminescence techniques by six laboratories. The settlements, Vesnianoje in Ukraine and Zaborie in Russia, are located in, respectively, proximal and distal locations relative to the Chernobyl Nuclear Power Plant. The luminescence determinations of cumulative dose in brick, after subtraction of the natural background dose, were translated to absorbed dose in air at a Reference Location using conversion factors derived from Monte Carlo simulations of photon transport. The simulations employed source distributions inferred from contemporary soil contamination data and also took into account heterogeneity of fallout deposition. This translation enables the luminescence determinations to be compared directly with values of cumulative absorbed dose obtained by computational modeling and also other dose reconstruction methods. For each sampled location the cumulative dose was calculated using three deterministic models, two of which are based on the attenuation of dose-rate with migration of radionuclides in soil and the third on historic instrumental gamma dose-rate data. The results of the comparison of the two methods indicate overall agreement within margins of +/-25%. The methodology developed is generally applicable and adaptable to areas contaminated by much lower levels of radioactive fallout in which brick buildings are found. AU - Bailiff, I.K.* AU - Stepanenko, V.F.* AU - Göksu, H.Y. AU - Botter-Jensen, L.* AU - Brodski, L.* AU - Chumak, V.* AU - Correcher, V.* AU - Delgado, A.* AU - Golikov, V.* AU - Jungner, H.* AU - Khamidova, L.G.* C1 - 3465 C2 - 21436 SP - 25-41 TI - Comparison of retrospective luminescence dosimetry with computational modeling in two highly contaminated settlements downwind of the Chernobyl NPP. JO - Health Phys. VL - 86 IS - 1 PB - Lippincott, Williams & Wilkins PY - 2004 SN - 0017-9078 ER - TY - JOUR AU - Fill, U.A. AU - Zankl, M. AU - Petoussi-Henß, N. AU - Siebert, M. AU - Regulla, D.F. C1 - 4132 C2 - 21864 SP - 253-272 TI - Adult female voxel models of different stature and photon conversion coefficients for radiation protection. JO - Health Phys. VL - 86 PY - 2004 SN - 0017-9078 ER - TY - JOUR AU - Gavrilin, Y.* AU - Khrouch, V.* AU - Shinkarev, S.* AU - Drozdovitch, V.* AU - Minenko, V.* AU - Shemiakina, E.* AU - Ulanowski, A. AU - Bouville, A.* AU - Anspaugh, L.* AU - Voillequé, P.* AU - Luckyanov, N.* C1 - 2879 C2 - 22078 SP - 565-585 TI - Individual thyroid dose estimation for a case-control study of Chernobyl related thyroid cancer among children of Belarus-Part I: 131I, short-lived radioiodines (132I, 133I, 135I) and short-lived radiotelluriums (131MTe and 132Te). JO - Health Phys. VL - 86 PY - 2004 SN - 0017-9078 ER - TY - JOUR AU - Höllriegl, V. AU - Röhmuß, M. AU - Oeh, U. AU - Roth, P. C1 - 5071 C2 - 21900 SP - 193-196 TI - Strontium biokinetics in humans: Influence of alginate on the uptake of ingested strontium. JO - Health Phys. VL - 86 PY - 2004 SN - 0017-9078 ER - TY - JOUR AU - Kis, Z. AU - Eged, K. AU - Voigt, G.* AU - Meckbach, R. AU - Müller, H. C1 - 2568 C2 - 21919 SP - 161-173 TI - Modeling of an industrial environment: external dose calculations based on Monte Carlo simulations of photon transport. JO - Health Phys. VL - 86 PY - 2004 SN - 0017-9078 ER - TY - JOUR AU - Semioshkina, N.A. AU - Voigt, G.* AU - Mukusheva, M.* AU - Bruk, G.* AU - Travnikova, I.* AU - Strand, P.* C1 - 5158 C2 - 22024 SP - 187-192 TI - Assessment of the current internal dose due to 137Cs and 90Sr for peaple living within the semipalatinsk test site, Kazakhstan. JO - Health Phys. VL - 86 PY - 2004 SN - 0017-9078 ER - TY - JOUR AU - Pröhl, G. C1 - 51637 C2 - 0 SP - 111-112 TI - Response to k. baverstock, m. thorne: The use of effective dose in retrospective dose assessment. JO - Health Phys. VL - 85 IS - 1 PY - 2003 SN - 0017-9078 ER - TY - JOUR AU - Tolstykh, E.I.* AU - Shishkina, E.A.* AU - Degteva, M.O.* AU - Ivanov, D.V.* AU - Shved, V.A.* AU - Bayankin, S.N.* AU - Anspaugh, L.R.* AU - Napier, B.A.* AU - Wieser, A. AU - Jacob, P. C1 - 9431 C2 - 21268 SP - 409-419 TI - Age dependencies of 90Sr incorporation in dental tissues : comparative analysis and interpretation of different kinds of measurements obtained for residents on the Techa River. JO - Health Phys. VL - 85 PY - 2003 SN - 0017-9078 ER - TY - JOUR AB - Bricks collected from a contaminated village (Muslyumovo) of the lower Techa river valley, Southern Urals, Russia, were measured using thermoluminescence and optically stimulated luminescence by four European laboratories and a U.S. laboratory to establish and compare the applied dose reconstruction methodologies. The bricks, collected from 60-100-year-old buildings, had accumulated a relatively high dose due to natural sources of radiation in the brick and from the surrounding environment. This work represents the results of a first international intercomparison of luminescence measurements for bricks from the Southern Urals. The luminescence measurements of absorbed dose in bricks collected from the most shielded locations of the same buildings were used to determine the background dose due to natural sources of radiation and to validate the age of the bricks. The absorbed dose in different bricks measured by four laboratories using thermoluminescence and optically stimulated luminescence at a depth of 10 +/- 2.5 mm from the exposed brick surface agreed within +/-21%. After subtraction of the natural background dose, the absorbed dose in brick due to contaminated river sediments and banks was calculated and found to range between 150 and 200 mGy. The cumulative doses in brick due to man-made sources of radiation at 100 and 130 mm depths in the bricks were also measured and found to be consistent with depth dose profiles calculated by Monte Carlo simulations of photon transport for possible source distributions. AU - Göksu, H.Y. AU - Degteva, M.O.* AU - Bougrov, N.G.* AU - Meckbach, R. AU - Haskell, E.H.* AU - Bailiff, I.K.* AU - Botter-Jensen, L.* AU - Jungner, H.* AU - Jacob, P. C1 - 9433 C2 - 20078 SP - 94-101 TI - First International Intercomparison of Luminescence Techniques Using Samples from the Teche River Valley. JO - Health Phys. VL - 82 IS - 1 PB - Lippincott, Williams & Wilkins PY - 2002 SN - 0017-9078 ER - TY - JOUR AU - Kreuzer, M.* AU - Brachner, A.* AU - Lehmann, F* AU - Martignoni, K.* AU - Wichmann, H.-E. AU - Grosche, B.* C1 - 22081 C2 - 20733 SP - 26-34 TI - Characteristics of the German uranium miners cohort study. JO - Health Phys. VL - 83 PY - 2002 SN - 0017-9078 ER - TY - JOUR AB - Following the Chernobyl accident many activities were conducted in Ukraine in order to define the radiological impact. Considered here are gamma spectrometric analyses of soil-depth-profile samples taken in the years 1988-1999, gamma spectrometric measurements of radionuclide concentration in soil samples taken in 1986, and measurements of external gamma-exposure rate in air. These data are analyzed in this paper to derive a reference" radionuclide composition and an attenuation function for the time-dependent rate of external gamma exposure that changes due to the migration of radiocesium into the soil column. An attenuation function for cesium is derived that consists of two exponential functions with half lives of 1.5 and 50 y. The dependencies of attenuation on direction and distance from the Chernobyl Nuclear Power Plant are also demonstrated. On the basis of these analyses the average individual and collective external gamma doses for the population of Ukraine are derived for 1986, 1986-2000, and 1986-2055. For the 1.4 million persons living in rural areas with Cs-137 contamination of >37 kBq m(-2), the collective effective dose from external exposure is estimated to be 7,500 person-Sv by the end of 2000. A critical group of 22,500 persons who received individual doses of >20 mSv is identified for consideration of increased social and medical attention." AU - Likhtarev, I.A.* AU - Kovgan, L.N.* AU - Jacob, P. AU - Anspaugh, L.R.* C1 - 9434 C2 - 20265 SP - 290-303 TI - Chernobyl Accident : Retrospective and Prospective Estimates of External Dose of the Population of Ukraine. JO - Health Phys. VL - 82 PB - Williams & Wilkins PY - 2002 SN - 0017-9078 ER - TY - JOUR AB - Due to lack of measurements of activity concentrations in air, the assessment of the inhalation dose of the population evacuated from the 30-km zone after the Chernobyl accident is not possible from continuous filter measurements. Since the evaluation of the inhalation dose in each settlement of the zone is of great interest for epidemiological purposes, an approach was chosen that utilizes the available data on ground deposition of 137Cs, a recently performed best estimate of the radionuclide vector and its spatial distribution as well as the radionuclide dependent deposition velocity. The derived inhalation dose values in the 30-km zone range between 3 mSv to 150 mSv effective dose for adults depending on the distance to the reactor site and the day of evacuation. For 1-y-old infants the values range between 10 to 700 mSv. In Chernobyl town, an effective inhalation dose of 25 mSv until evacuation day was assessed. Thyroid doses due to inhalation ranged from 0.02 to 1 Sv for adults, for 1-y-old infants from 0.02 to 6 Sv. The inhalation dose in each settlement of the 30-km zone is approximately 8-13 times higher than the external exposure in each settlement if evacuation of the settlement occurred at an early stage. For settlements with evacuation at a later stage (day 10 or later) the inhalation dose was about 50-70% higher than the external dose. The dominant contribution to the effective inhalation dose comes from 131I (about 40%) and tellurium and rubidium isotopes (about 20-30%). Despite high zirconium and cerium ground depositions, zirconium and cerium isotopes contribute rather little to the inhalation dose which is mainly due to the great particle sizes to which they are attached. The relative contribution of short-lived radionuclides is, despite higher activities than at greater distances, less than 5%. AU - Mück, K.* AU - Pröhl, G. AU - Likhtarev, I.* AU - Kovgan, L.* AU - Golikov, V.* AU - Zeger, J.* C1 - 9436 C2 - 20303 SP - 157-172 TI - Reconstruction of the Inhalation Dose in the 30-KM Zone after the Chernobyl Accident. JO - Health Phys. VL - 82 PB - Williams & Wilkins PY - 2002 SN - 0017-9078 ER - TY - JOUR AB - The radionuclide vector in the release plume from the destroyed unit 4 of the Chernobyl Nuclear Power Plant was assessed. Emphasis was laid on radionuclides relevant for the internal dose, including those with short half-lives, and on the radionuclide vector in the 30-km zone where practically no data in air or foodstuff are available. An evaluation of data was performed by comparing core analysis data and actual measurements of air filters and deposition data. The derived nuclide vector is consistent with most measurements and core analysis data. The ratios of the various radionuclides with regard to the guide isotope 137Cs vary both with direction of release and with increasing distance from the power plant. The variation and its causes are discussed, and a credible, consistent model for the vector at arbitrary distances from the nuclear power plant, in particular with regard to non-volatile radionuclides, is given. In that way the observed large discrepancies of the radionuclide vector determined by Russian and Ukrainian researchers, and those measured in Central and Northern European are explained by the fact that 90Sr, 95Zr, 140Ba, and 144Ce, which showed a much higher ratio to 137Cs close to the reactor than at 1,000 km distance, were attached to particle sizes of 8 µm and thus quicker deposited than the volatile radionuclides which were attached to 1 µm particulates on average. Also, the 131I to 137Cs ratio changes with distance by almost one order of magnitude which is explained by the higher deposition velocity of iodine. AU - Mück, K.* AU - Pröhl, G. AU - Likhtarev, I.* AU - Kovgan, L.* AU - Meckbach, R. AU - Golikov, V.* C1 - 10139 C2 - 20304 SP - 141-156 TI - A Consistent Radionuclide Vector after the Chernobyl Accident. JO - Health Phys. VL - 82 PB - Williams & Wilkins PY - 2002 SN - 0017-9078 ER - TY - JOUR AB - As a consequence of the Chernobyl accident, about 50,000 people were evacuated from the settlements in the 30-km zone around the reactor in the period 3-11 d after the accident. As no countermeasures were implemented in the early phase, people continued to consume milk and some leafy vegetables. In this paper, average effective ingestion doses are modeled for evacuees. Input data for the assessment are the 137Cs activity per unit area, the ratios of the radionuclides relative to 137Cs, the mean day of evacuation, and intake rates for milk and green vegetables. The transfer of radionuclides from deposition to humans is estimated by modeling radionuclide interception by vegetation, weathering, and the time-dependent transfer of radionuclides to milk taking into account site-specific agricultural practices. Depending on the evacuation day and site, the estimated ingestion doses for the settlements are in the range of 20 to 1,300 mSv and 3 to 180 mSv for infants and adults, respectively. 131I is by far the most important isotope, the ingestion dose due to 133I is more than one order of magnitude lower. The most exposed organ is the thyroid, inducing more than 80% and 50% of the ingestion dose for infants and adults. The ingestion doses are compared to the doses due to inhalation and external exposure. The internal dose exceeds the external by a factor of about 2-10 for adults and 2-40 for 1-y-old infants depending on site and evacuation day. The thyroid doses assessed for the evacuees are consistent with results achieved in studies performed in areas outside the 30-km zone. AU - Pröhl, G. AU - Mück, K.* AU - Likhtarev, I.* AU - Kovgan, L.* AU - Golikov, V.* C1 - 9435 C2 - 20302 SP - 173-181 TI - Reconstruction of the Ingestion Doses Received by the Population Evacuated from the Settlements in the 30-KM Zone Around the Chernobyl Reactor. JO - Health Phys. VL - 82 PB - Williams & Wilkins PY - 2002 SN - 0017-9078 ER - TY - JOUR AB - Knowledge of the mode of deposition (wet or dry) during the main fallout period following the Chernobyl accident in late April 1986 is one of the most important parameters in environmental reconstruction of the radiation dose to the thyroid from 113I following the accident. Meteorological data are available only for a small number of locations, but routine field measurements in 1997 of exposure rates in areas still contaminated by 137Cs revealed that there is a natural indicator of wet deposition. Follow-up measurements confirmed that there is a significant difference in exposure rates measured on different sides at the bases of inclined birch trees in areas of wet deposition. In such areas, the exposure rates measured on the sheltered" sides of the trees were on average 2.3+/-0.2 times those measured on the unsheltered side. In areas of dry deposition the comparable ratio was 1.01+/-0.02 for similarly inclined trees. Because birch trees are a common feature in the contaminated territories, this effect has a wide potential for use in determining whether the fallout in many areas was due to wet or dry deposition." AU - Stepanenko, V.F.* AU - Gavrilin, Yu.I.* AU - Snykov, V.P.* AU - Shevchuk, V.E.* AU - Göksu, H.Y. AU - Voilleque, P.G.* AU - Orlov, M.Yu.* C1 - 9432 C2 - 20077 SP - 240-243 TI - Elevated Exposure Rates Under Inclined Birch Trees Indicate the Occurrence of Rainfall During Radioactive Fallout from Chernobyl. JO - Health Phys. VL - 82 IS - 2 PB - Lippincott, Williams & Wilkins PY - 2002 SN - 0017-9078 ER - TY - JOUR AU - Zankl, M. AU - Petoussi-Henß, N. C1 - 10140 C2 - 20183 SP - 254-256 TI - Conversion Coefficients based on the Vip-Man Anatomical Model for Photons. JO - Health Phys. VL - 82 PB - Lippincott, Williams & Wilkins PY - 2002 SN - 0017-9078 ER - TY - JOUR AU - Romanyukha, A.A.* AU - Seltzer, S.M.* AU - Desrosiers, M.* AU - Ignatiev, E.A.* AU - Ivanov, D.V.* AU - Bayankin, S.* AU - Degteva, M.O.* AU - Eichmiller, F.C.* AU - Wieser, A. AU - Jacob, P. C1 - 21884 C2 - 20109 SP - 554-566 TI - Correction Factors in the EPR Dose Reconstruction for Residents of the Middle and Lower Techa Riverside. JO - Health Phys. VL - 81 PY - 2001 SN - 0017-9078 ER - TY - JOUR AB - This paper describes the effect on over 3,000 sets of internal dose estimates of using photon Specific Absorbed Fractions (SAFs) calculated using two different types of phantoms, specifically the MIRD-type anthropomorphic phantom originally developed by Snyder and the new adult male voxel phantom, GOLEM, developed at GSF, The SAFs based on the MIRD-type phantom are currently used by the International Commission on Radiological Protection (ICRP) in internal dose calculations, but there are suggestions of moving towards SAFs generated from voxel phantoms, thus there is an interest in the potential differences in internal doses. Overall, it is found that some tissue doses calculated using the voxel phantoms can differ significantly from those of the MIRD-type phantom; however, the effective dose appears to be quite robust to changes in photon SAFs. AU - Smith, T.J.* AU - Phipps, A.W.* AU - Petoussi-Henß, N. AU - Zankl, M. C1 - 9430 C2 - 19805 SP - 477-485 TI - Impact on internal doses of photon safs derived with the GSF adult male voxel phantom. JO - Health Phys. VL - 80 IS - 5 PB - Lippincott Williams & Wilkins PY - 2001 SN - 0017-9078 ER - TY - JOUR AU - Gerken, M. AU - Kreienbrock, L. AU - Wellmann, J. AU - Kreuzer, M. AU - Wichmann, H.-E. C1 - 21309 C2 - 19424 SP - 268-278 TI - Models for retrospective quantification of indoor radon exposure in case-control studies. JO - Health Phys. VL - 78 PY - 2000 SN - 0017-9078 ER - TY - JOUR AU - Giussani, A.* AU - Cantone, M.C.* AU - de Bartolo, D.* AU - Roth, P. AU - Werner, E. C1 - 21164 C2 - 19209 SP - 46-52 TI - Internal dose for ingestion of molybdenum radionuclides based on a revised biokinetic model. JO - Health Phys. VL - 78 PY - 2000 SN - 0017-9078 ER - TY - JOUR AU - Likhtarev, I.A.* AU - Kovgan, L.* AU - Vavilov, S.E.* AU - Perevoznikov, O.N.* AU - Litvinets, L.N.* AU - Anspaugh, L.R.* AU - Jacob, P. AU - Pröhl, G. C1 - 21546 C2 - 19669 SP - 341-357 TI - Internal exposure from the ingestion of foods contaminated by 137Cs after the Chernobyl accident-Report 2. Ingestion doses of the rural population of Ukraine up to 12 Y after the accident (1986-1997). JO - Health Phys. VL - 79 PY - 2000 SN - 0017-9078 ER - TY - JOUR AU - Romanyukha, A.A.* AU - Ignatiev, E.A.* AU - Vasilenko, E.K.* AU - Drozhko, E.G.* AU - Wieser, A. AU - Jacob, P. AU - Keirim-Markus, I.B.* AU - Kleschenko, E.D.* AU - Nakamura, N.* AU - Miyazawa, C.* C1 - 21836 C2 - 20028 SP - 15-20 TI - EPR Dose Reconstruction for Russian Nuclear Workers. JO - Health Phys. VL - 78 PY - 2000 SN - 0017-9078 ER - TY - JOUR AU - Golikov, V.* AU - Balonov, M.* AU - Erkin, V.* AU - Jacob, P. C1 - 21163 C2 - 19207 SP - 654-661 TI - Model validation for external doses due to environmental contaminations by the Chernobyl accident. JO - Health Phys. VL - 77 PY - 1999 SN - 0017-9078 ER - TY - JOUR AU - Kreienbrock, L. AU - Poffijn, A.* AU - Tirmarche, M.* AU - Feider, M.* AU - Kies, A.* AU - Darby, S.C.* C1 - 20907 C2 - 18952 SP - 558-563 TI - Intercomparison of passive radon-detectors under field conditions in epidemiological studies. JO - Health Phys. VL - 76 PY - 1999 SN - 0017-9078 ER - TY - JOUR AU - Zankl, M. C1 - 20777 C2 - 18826 SP - 162-170 TI - Personal dose equivalent for photons and its variation with dosimeter position. JO - Health Phys. VL - 76 PY - 1999 SN - 0017-9078 ER - TY - JOUR AU - Giussani, A. AU - Cantone, M.C.* AU - de Bartolo, D.* AU - Roth, P. AU - Werner, E. C1 - 21073 C2 - 19103 SP - 479-486 TI - A revised model of molybdenum biokinetics in humans for application in radiation protection. JO - Health Phys. VL - 75 PY - 1998 SN - 0017-9078 ER - TY - JOUR AB - The time-dependent radioecological simulation model ECOSYS-87 has been developed to assess the radiological consequences of short-term depositions of radionuclides. Internal exposure via inhalation and ingestion as well as external exposure from the passing cloud and from radioactivity deposited on the ground, are included in the model. The site-specific parameter values of the model are representative of Southern German agricultural conditions, however, the model design facilitates adaption to other situations. The ingestion dose is calculated as a function of time considering 18 plant species, 11 animal food products, and 18 processed products. The ingestion and inhalation exposure is estimated for six age groups using age-dependent consumption and inhalation rates and age-dependent dose factors. Results demonstrate a pronounced influence regarding the time of year (season) of deposition on the ingestion dose and on the relative importance of the exposure pathways. Model results compare well with activities in foods measured after the Chernobyl accident. AU - Müller, H.M. AU - Pröhl, G. C1 - 40323 C2 - 0 SP - 232-252 TI - Ecosys-87: A dynamic model for assessing radiological consequences of nuclear accidents. JO - Health Phys. VL - 64 IS - 3 PY - 1993 SN - 0017-9078 ER - TY - JOUR AU - Sevc, J. AU - Tomasek, L. AU - Kunz, E. AU - Placek, V. AU - Chmelevsky, D. AU - Barclay, D. AU - Kellerer, A.M. C1 - 20299 C2 - 13488 SP - 355-369 TI - A Survey of the Czechoslovak Follow-up of Lung Camcer Mortality in Uranium Miners. JO - Health Phys. VL - 64 PY - 1993 SN - 0017-9078 ER - TY - JOUR AB - The distribution and the biological half-lives of 137Cs in poultry after continuous intake of foodstuffs contaminated by the Chernobyl fallout were studied in order to determine transfer coefficients to yolk, albumen, and shell of eggs as well as transfer coefficients to chicken meat. Mean values for laying hens were found to be 0.2 d kg-1 (whole consumable egg), 1.2 d kg-1 (leg meat), and 1.6 d kg-1 (breast meat) when radiocesium was fed in contaminated grass pellets, and about twice as large [i.e., 0.4 d kg- 1 (whole consumable egg), 2.8 d kg-1 (leg meat), and 3.0 d kg-1 (breast meat)] when radiocesium was fed in contaminated wheat. Reducing effects of the feed additive ammonium-ferric-cyano-ferrate in concentrations of 0.66 g kg-1 of feed mixture on the contamination of hen products were quantified to be a factor of 3 to 4 (whole consumable egg and meat after grass pellet feeding) and 8 to 14 (whole consumable egg and meat after wheat feeding). A drastically higher reduction with an ammonium-ferric-cyanoferrate dose twice as large (1.33 g kg-1) was achieved. For broiler chickens, activity concentration ratios of meat to feed were derived for various fattening periods, with mean values of about 0.3 (leg), 0.4 (breast), and 0.2 (liver). The addition of ammonium-ferric-cyano-ferrate reduced the activity concentrations in meat by factors of more than 6. AU - Voigt, G.M. AU - Müller, H.M. AU - Paretzke, H.G. AU - Bauer, T.R. AU - Röhrmoser, G.M. C1 - 40397 C2 - 0 SP - 141-146 TI - 137Cs transfer after chernobyl from fodder into chicken meat and eggs. JO - Health Phys. VL - 65 IS - 2 PY - 1993 SN - 0017-9078 ER - TY - JOUR AB - When applying the standard method of in-situ gamma spectrometry to determine deposited radionuclide activities, an assumption is needed regarding the depth distribution of radionuclides in the ground. The method can be improved by assessing, from information contained in the spectrum, the attenuation of the radiation by the soil and vegetation. By comparing the count rates of the x ray and the gamma-ray lines of its daughter nuclide 137mBa, the 137Cs activity per area can be determined. The range of applicability of the method is discussed by means of an uncertainty analysis, and the method is applied to post-Chernobyl measurements. A comparison with the results of the standard method of in-situ spectrometry demonstrates the progress achieved by the proposed method. Nevertheless, the method still has some shortcomings for the peak analysis that could be improved by better detector resolution or better computer software. AU - Rybacek, K. AU - Jacob, P. AU - Meckbach, R. C1 - 40646 C2 - 0 SP - 519-528 TI - In-situ determination of deposited radionuclide activities: Improved method using derived depth distributions from the measured photon spectra. JO - Health Phys. VL - 62 IS - 6 PY - 1992 SN - 0017-9078 ER - TY - JOUR AB - After the Chernobyl accident, the activity concentrations of radiocesium were measured in both the meals served at the cafeteria of a research center and in the employees eating there. The time-dependent means of monthly 137Cs activities in meals and people show a similar distribution pattern with highest values between March and July 1987, i.e., only 1 y after the accident. In meals, the highest activities were found when the menu consisted of pork, milk, or milk products. The 50-y cumulative effective dose calculated from the whole-body measurements is 0.21 mSv for male and 0.15 mSv for female employees. Cafeteria food contributed only a small share to this exposure. AU - Voigt, G.M. AU - Paretzke, H.G. C1 - 40655 C2 - 0 SP - 574-575 TI - 137Cs uptake with cafeteria food after the Chernobyl accident. JO - Health Phys. VL - 63 IS - 5 PY - 1992 SN - 0017-9078 ER - TY - JOUR AB - In a recent recommendation, the International Commission on Radiological Protection substituted the effective dose equivalent, H(E), with a similar quantity-the 'effective dose,' E-changing both the set of organs considered and the respective weighting factors. To quantify the impact of these changes, calculations of E and H(E) were performed for various photon energies and external irradiation geometries using a Monte Carlo code and mathematical anthropomorphic phantoms to which an esophagus was introduced for this purpose. For energies >15 keV, E < H(E), the difference depending on photon energy and exposure geometry. AU - Zankl, M. AU - Petoussi, N. AU - Drexler, G.G. C1 - 33294 C2 - 35480 SP - 395-399 TI - Effective dose and effective dose equivalent - The impact of the new ICRP definition for external photon irradiation. JO - Health Phys. VL - 62 IS - 5 PY - 1992 SN - 0017-9078 ER - TY - JOUR AU - Müller, W.A. AU - Luz, A. AU - Murray, A.B. AU - Linzner, U. C1 - 18254 C2 - 11472 SP - 305-310 TI - Induction of Lymphoma and Osteosarcoma in Mice by Single and Protracted Low Alpha-Doses. JO - Health Phys. VL - 59 PY - 1990 SN - 0017-9078 ER - TY - JOUR AB - Internal doses from the short-lived α-emitter 224Ra were given to 4-wk-old female NMRI mice. One group of about 300 animals received a single injection of 18.5 kBq 224Ra kg-1 body weight, corresponding to a mean skeletal α dose of 0.15 Gy. A second group of about 300 animals received the same total amount of 224Ra in the form of 72 fractions of 257 Bq kg-1 each, applied twice weekly during 36 wk. The fractionated group received the same final mean total skeletal dose of 0.15 Gy as the single injected group, but with a mean skeletal dose rate of 1 mGy d-1. A rather high incidence, 13.5% (40/296), of early malignant lymphomas was observed in the fractionated group during and shortly after the injection period, followed by a 7% incidence (21/296) of osteosarcomas during the second half of the animals' lifetime. The group with a single injection did not develop early lymphomas but did develop osteosarcomas later with an incidence of 5.8% (17/295). The occurrence of osteosarcomas was similar up to day 800 in the two experimental groups. Surprisingly, however, after this period no additional case of osteosarcoma was observed in the single-injected group, whereas one-third of all osteosarcomas occurred after day 800 in the protracted group. The additional later occurrence of osteosarcomas in the protracted group clearly indicates a longer lasting induction effect on osteosarcomas, or a promoting effect in older age, for this kind of treatment. AU - Müller, W.A. AU - Luz, A. AU - Murray, A.B. AU - Linzner, U. C1 - 41802 C2 - 0 SP - 305-310 TI - Induction of lymphoma and osteosarcoma in mice by single and protracted low α doses. JO - Health Phys. VL - 59 IS - 3 PY - 1990 SN - 0017-9078 ER - TY - JOUR AB - For three plants from a peat bog (Trichophorum caespitosum, Molinia coerulea, Calluna vulgaris) the concentration of 137Cs, the ratio 137Cs:134Cs, and stable K was determined in intervals of about 14 d from June to November 1987. The reslts show that for two grasses, Trichophorum caespitosum and Molinia coerulea (which have only perennial roots but sprout every year while the old leaves wither), the concentration of 137Cs decreased considerably during the growing season (1800-240, respectively, 4000-320 Bq kg-1 dry weight). A remarkably similar behavior was observed for the seasonal variability of K and radiocesium in the two grass species, which resulted in a nearly constant ratio of 137Cs:K during the year. In contrast, for the evergreen plant Calluna vulgaris (heather) which was contaminated surficially by the Chernobyl fallout, the concentrations of K and 137Cs were rather constant during 1987 (leaves about 10,000; stems about 5000 Bq kg-1 dry weight), even though radiocesium was taken up by the leaves and transported within the plant. For the two grasses, the plant:soil concentration ratios (CR) were obtained separately for total 137Cs, 137Cs from the global fallout, and Chernobyl-derived 137Cs. The CR of 137Cs from the global fallout decreased for Trichophorum caespitosum from 1.9 in the spring to 0.08 in the autumn, and for Chernobyl-derived 137Cs from 1.4 to 0.2. For Molinia coerulea, a similar behavior was observed. Possible reasons for the seasonal variability of the CR values and the different behavior of 137CS from the global fallout and from the Chernobyl debris are discussed. The CR predicted for these plants with help of the distribution coefficient K(d) for the sorption of 137Cs by the peat soil (Baes equation) agreed faily well with the observed average CR during the growing season. AU - Bunzl, K.W. AU - Kracke, W. C1 - 33852 C2 - 40345 SP - 593-600 TI - Seasonal variation of soil-to-plant transfer of K and fallout 134,137Cs in Peatland vegetation. JO - Health Phys. VL - 57 IS - 4 PY - 1989 SN - 0017-9078 ER - TY - JOUR AU - Voigt, G. AU - Müller, H. AU - Pröhl, G. AU - Paretzke, H.G. AU - Probstmeier, G. AU - Röhrmoser, G. AU - Hofmann, P. C1 - 18145 C2 - 11005 TI - Experimental Determination of Transfer Coefficients of 137Cs and 131 from Fodder into Milk of Cows and Sheep after the Chernobyl Accident. JO - Health Phys. PY - 1989 SN - 0017-9078 ER - TY - JOUR AB - Following the Chernobyl accident in April 1986, the transfer of 131I and 137Cs from feed to milk was studied under experimental and common agricultural conditions. From measurements in different dairy farms in Southern Bavaria, equilibrium transfer coefficients for cow's milk were calculated to be 0.003 d L-1 (range 0.0015 to 0.005) for 131I and 0.003 d L-1 (range 0.0025 to 0.004) for 137Cs. In feeding experiments with cows and sheep under more controlled conditions, milk transfer coefficients of 0.007 d L-1 (range 0.0055 to 0.0081) for 131I and 0.003 d L-1 (range 0.0023 to 0.0053) for 137Cs were obtained for cows, while for sheep the 137Cs transfer coefficient was higher: 0.06 d L-1. The kinetics of the Cs transfer from fodder to cow's milk can be described by two exponential terms assuming biological half-lives in milk of 1-2 d and 10-20 d. The use of a fast component with 1.5 d and a fraction of 0.8, and a slow component with 15 d, gives a good approximation to the kinetics for all cows in this experiment. AU - Voigt, G.M. AU - Müller, H.M. AU - Pröhl, G. AU - Paretzke, H.G. C1 - 33843 C2 - 40347 SP - 967-973 TI - Experimental determination of transfer coefficients of 137Cs and 131I from fodder into milk of cows and sheep after the Chernobyl accident. JO - Health Phys. VL - 57 IS - 6 PY - 1989 SN - 0017-9078 ER - TY - JOUR AU - Jacobi, W. C1 - 17444 C2 - 10349 SP - 845-53 TI - Environmental Radioactivity and Man - The 1988 Sievert Lecture. JO - Health Phys. VL - Dec;55(6) PY - 1988 SN - 0017-9078 ER - TY - JOUR AU - Jacobi, W. C1 - 41816 C2 - 36163 SP - 845-853 TI - Environmental radioactivity and man : The 1988 Sievert lecture. JO - Health Phys. VL - 55 IS - 6 PY - 1988 SN - 0017-9078 ER - TY - JOUR AU - Müller, W.A. AU - Linzner, U. AU - Luz, A. C1 - 42066 C2 - 0 SP - 461-463 TI - Early induction of leukemia (malignant lymphoma) in mice by protracted low α doses. JO - Health Phys. VL - 54 IS - 4 PY - 1988 SN - 0017-9078 ER - TY - JOUR AB - The science of radiation protection is a fundamental outgrowth of peaceful and military applications of ionizing radiation and the use of nuclear energy. Scientific progress in radiation protection has not, however, been as dramatic as progress in other scientific endeavors, because many users of ionizing radiation have perceived that the major technical and institutional problems have already been solved. This misperception is not based on solid fact and is not shared by radiation protection professionals, who have a broader vision of both past achievements and problems remaining in this area. Experience gained as a consequence of the Chernobyl accident has highlighted new problems and demonstrated the urgency of finding better answers to some old questions. This paper addresses the future impact of the recent Chernobyl accident on the science of radiation protection. In summary, the accident demonstrated that particular emphasis should be directed toward: - Improvement of dosimetric and health-effects models for predicting the consequences of exposure of the public to low doses of ionizing radiation. - Development of optimized, realistic countermeasures and improvement in emergency preparedness. - Education of the public, including students, scientists and politicians with regard to radiation protection issues. - Development of advanced computer programs and radiation instruments for evaluating reactor accidents and their consequences. - Transfer of learned concepts, methods and approaches to other scientific fields, such as environmental sciences, toxicology, pharmacology, etc. AU - Paretzke, H.G. C1 - 42495 C2 - 36252 SP - 139-143 TI - The impact of the Chernobyl accident on radiation protection. JO - Health Phys. VL - 55 IS - 2 PY - 1988 SN - 0017-9078 ER - TY - JOUR AU - Rozman, K.K. AU - Freeman, R.A. AU - Wilson, G. C1 - 17439 C2 - 10009 TI - Physiological Pharmacokinetic Model for Hexachlorbenzene in the Rat. JO - Health Phys. PY - 1988 SN - 0017-9078 ER - TY - JOUR AU - Voigt, G. AU - Ennis, M.E. AU - Johnson, J.E. AU - Ward, G.M. C1 - 17351 C2 - 9919 TI - A Specific Activity Effect in the Metabolism of Technetium. JO - Health Phys. VL - (Feb. 88) PY - 1988 SN - 0017-9078 ER - TY - JOUR AU - Bunzl, K.W. AU - Kracke, W. C1 - 41020 C2 - 36114 SP - 540-542 TI - Accumulation of fallout 137Cs in some plants and berries of the family Ericaceae. JO - Health Phys. VL - 50 IS - 4 PY - 1986 SN - 0017-9078 ER - TY - JOUR AB - Lung retention of 57Co in dogs after the inhalation of physically and chemically uniform particles of Co compounds was similar, indicating little biological variability. The retention of Co oxide particles ranging from 0.3 [mu]m to 2.7 [mu]m geometric diameter, however, depended markedly on their physicochemical parameters. Measuring the retention by a gamma camera, and analyzing excreta and blood samples enabled the distinction of different clearance pathways from the lungs particularly with the use of results of some metabolic studies. Particle dissolution was the predominant clearance pathway. Particle dissolution half times ranged from 6 to 80 d proportional to the size of the particles. organ analysis yielded information on the fate of the long-term burden of Co in the lungs and other organs. A fraction less than 10% of the initial lung burden was retained in the lungs of all dogs with a biological half time of 400 d presumably after being transformed into a nonparticulate state. There were cellular structures in the tracheobronchial tree which accumulated Co significantly. These studies on dogs suggest the dose after human exposure to well-defined Co aerosols can be accurately estimated. Whereas risk assessment after the exposure to undefined aerosols containing radionuclides of Co will mostly be impossible because retention varies widely with the varying physicochemical properties of the aerosol particles. AU - Kreyling, W.G. AU - Ferron, G.A. AU - Haider, B. C1 - 41935 C2 - 0 SP - 773-795 TI - Metabolic fate of inhaled Co aerosols in beagle dogs. JO - Health Phys. VL - 51 IS - 6 PY - 1986 SN - 0017-9078 ER - TY - JOUR AB - For external photon radiation, conversion factors between organ doses and the quantities normally measured in radiation protection were determined experimentally using an anthropomorphic phantom and thermoluminescent dosimeters. The measurements were made for different energies and irradiation geometries. As normalization quantities, the exposure measured in free air and the dose equivalent in soft tissue measured at a personal dosimeter site were used. The results are compared with conversion factors calculated by other authors. AU - Thomasz, E. AU - Eckerl, H. AU - Drexler, G.G. C1 - 33125 C2 - 35565 SP - 897-905 TI - Experimental determination of conversion factors between organ doses and measured quantities for external photon irradiation. JO - Health Phys. VL - 49 IS - 5 PY - 1985 SN - 0017-9078 ER - TY - JOUR AU - Williams, G.V. AU - Jankowski, J. AU - Swanson, W.P. AU - Drexler, G.G. C1 - 41382 C2 - 0 SP - 94-99 TI - Comparison of experimental and theoretical depth doses in the ICRU sphere using 137Cs. JO - Health Phys. VL - 49 IS - 1 PY - 1985 SN - 0017-9078 ER - TY - JOUR AU - Bunzl, K.W. AU - Kracke, W. C1 - 42310 C2 - 0 SP - 466-470 TI - Fallout (239/240)Pu and 137Cs in animal livers consumed by man. JO - Health Phys. VL - 46 IS - 2 PY - 1984 SN - 0017-9078 ER - TY - JOUR AB - An attempt was made to show if and to what extent the 137Cs transfer from soil to plants (grass) in forest clearings and grassland is related closely enough to different soil parameters to make it worthwhile to develop mathematical models for the prediction of transfer coefficients for certain plants and sites based solely on soil parameters. For this reason 62 soil samples from 0- to 5-cm in depth as well as from 5- to 10-cm in depth were measured for worldwide 137Cs fallout and analyzed for exchangeable potassium content, total potassium content, clay fraction, potential exchange capacity, pH value and carbon content. For both ecosystems, large variations of the transfer coefficients were observed: between 0.01 and 0.1 for grassland and 0.05 and 6 for forest clearings. Correlations, such as has been found between soil parameters, specific activities of the plants and transfer coefficients can in principle be integrated into different calculations for the estimation of radiation burden. AU - Kühn, W. AU - Handl, J. AU - Schuller, P. C1 - 41237 C2 - 0 SP - 1083-1093 TI - The influence of soil parameters on 137Cs+-uptake by plants from long-term fallout on forest clearings and grassland. JO - Health Phys. VL - 46 IS - 5 PY - 1984 SN - 0017-9078 ER - TY - JOUR AB - In a large series of experiments, fractionated injections of short-lived bone-seekers have been shown in many cases to cause a remarkable increase of the osteosarcoma incidence compared with a single administration of the same total skeletal dose. This effect has been observed with both alpha- and beta-emitters. In addition the latency period was shortened by protracting the dose. The total skeletal doses investigated ranged between 0.9 and 20 Gy for alpha-emitters (224Ra and 227Th) and between 28 and 112 Gy for the beta-emitter (177Lu). In all cases the protracted dose had higher or at least equal effects when compared with a single application. Reference experiments with long-lived alpha- and beta-emitting bone-seeking nuclides (226Ra and 90Sr) showed that the incidence of osteosarcomas per Gy was sometimes lower than that observed when the same skeletal dose was applied by protraction of short-lived radionuclides. The dependence of osteosarcoma incidence on dose-time distribution, duration of internal irradiation, and radiation quality is discussed. In this context the possibility that the critical initial dose rate may be related to the initiating event within the multi-stage hypothesis of carcinogenesis is considered. AU - Müller, W.A. AU - Luz, A. AU - Schäffer, E.H. AU - Gössner, W. C1 - 27606 C2 - 32763 SP - 203-212 TI - The role of time-factor and RBE for the induction of osteosarcomas by incorporated short-lived bone-seekers. JO - Health Phys. VL - 44 IS - Suppl 1 PB - Pergamon PY - 1983 SN - 0017-9078 ER - TY - JOUR AB - The concentration of the radionuclides (239/240)Pu, 137Cs, 90Sr and 40K depends, considerably, on the type of honey collected by the bees. Therefore, the use of honey samples as bioindicators for the above radionuclides will, in general, require the determination of the nature of the honey by a pollen analysis. AU - Bunzl, K.W. AU - Kracke, W. C1 - 41889 C2 - 40465 SP - 554-558 TI - 239/240Pu, 137Cs, 90Sr, and 40K in different types of honey. JO - Health Phys. VL - 41 IS - 3 PY - 1981 SN - 0017-9078 ER - TY - JOUR AB - Results from a Monte-Carlo simulation have been presented for the transport of 137Cs via the pasture-cow-milk pathway, taking into account the uncertainties and naturally occurring fluctuations in the rate constants. The results of the stochastic model calculations characterize the activity concentration at a given time t and provide a great deal more information for analysis of the environmental transport of radionuclides than deterministic calculations. Moreover, it permits an estimate of the variation of the physico-chemical behaviour of radionuclides in the environment in a more realistic way than by using only the highest transfer coefficients in deterministic approaches, which can lead to non-realistic overestimates of the probability with which high activity levels will be encountered. AU - Matthies, M. AU - Eisfeld, K. AU - Paretzke, H.G. AU - Wirth, E. C1 - 41039 C2 - 0 SP - 764-769 TI - Stochastic calculations for radiation risk assessment: A Monte-Carlo approach to the simulation of radiocesium transport in the pasture-cow-milk food chain. JO - Health Phys. VL - 40 IS - 5 PY - 1981 SN - 0017-9078 ER - TY - JOUR AB - A method is presented for determining the concentrations of airborne 210Pb and 210Po. The method employs α spectrometry to measure the count rate of 210 Po present on an electrostatic filter sample at two post-sampling times. The individual air concentrations of 210Po and 210Pb can be calculated from equations given. Sensitivity of the procedure is about 0.2 fCi 210Po per m3 of air. The method was applied to the study of long-term variations and frequency distributions of 210Po and 210Pb concentrations in surface air at a nonpolluted location about 10 km outside of Munich, F.R.G., from 1976 through 1979. During this period the average concentration levels were found to be 14.2 fCi210Pb per m3 of air and 0.77 fCi 210Po per m3 of air, respectively. AU - Winkler, R.A. AU - Hoetzl, H. AU - Chatterjee, B. C1 - 42507 C2 - 0 SP - 495-503 TI - Analysis of 210Pb and 210Po concentrations in surface air by an α spectrometric method. JO - Health Phys. VL - 41 IS - 3 PY - 1981 SN - 0017-9078 ER - TY - JOUR AB - Slime from small water-conducting canals in tidal land is sometimes excavated by farmers and applied to the surrounding grassland. The canals are interconnected with rivers near the sea, and nuclear power stations are sited at those rivers. There is a possibility, as a consequence of the tide, that small amounts of radioactive contamination from the rivers will be deposited on the slime in the canals. Therefore, an investigation was made to determine the contamination of grass caused by slime containing 137Cs and 60Co. AU - Handl, J. AU - Kuehn, W. C1 - 41325 C2 - 0 SP - 703-705 TI - Determination of transfer coefficients for 137Cs and 60Co in a slime-soil-grassland ecosystem. JO - Health Phys. VL - 38 IS - 4 PY - 1980 SN - 0017-9078 ER - TY - JOUR AB - The concentrations of 210Pb, 210Po and stable lead were determined in liver and kidneys of 40 animals from a mainly agricultural region with little traffic or industry. Median liver concentrations of 18.0 pCi 210Pb and 33.3 pCi 210Po per kg wet tissue, and median kidney concentrations of 44.0 pCi 210Pb and 178.5 pCi 210Po/kg wet tissue were observed. The specific activity of 210Pb was 161 and 132 nCi 210Pb/g Pb in liver and kidneys, respectively. On the average, the kidneys contained 2.37 more 210Pb, 5.05 more 210Po and 2.89 more Pb than the livers. The ratio 210Po/210Pb was 2.18 in the liver and 3.95 in the kidneys. Correlation analysis revealed significant correlations between 210Po in liver and kidneys, Pb in liver and kidneys, 210Po and 210Pb in kidneys, 210Pb and Pb in liver, 210Pb and Pb in kidneys, 210Po and Pb in liver, as well as 210Po and Pb in kidneys. No significant correlation was observed between the concentrations of either 210Po or 210Pb in liver or kidneys and the age of the animals. AU - Bunzl, K.W. AU - Kracke, W. AU - Kreuzer, W. C1 - 40954 C2 - 40460 SP - 323-330 TI - 210Pb and 210Po in liver and kidneys of cattle. I. Animals from an area with little traffic or industry. JO - Health Phys. VL - 37 IS - 3 PY - 1979 SN - 0017-9078 ER - TY - JOUR AB - 224Ra (half-life 3.64 days) or 227Th (half-life 18.7 days) were intraperitoneally injected in 3-4 week old NMRI mice. The spontaneous osteosarcoma incidence was about 1% in females and 0% in males. The distribution of 224Ra within the skeleton showed the highest concentration in the long bones, somewhat lower values in the vertebral column, increasing towards the lower part. Single injections of 224Ra with activities between 1 and 100μCi/kg, corresponding to mean skeletal doses (m.s.d) of 30-3000 rad resulted in an osteosarcoma incidence of 7% in females at the lowest activity applied and reached a maximum of 22% at higher activities, whereas in males the maximum was 8.5%. Single injections of 227Th with activities between 0.1 and 50μCi/kg of 227Th (corresponding to m.s.d of 20-10,000 rad) produced an osteosarcoma incidence of 3% at the lowest activity applied and a maximum incidence of 60% at 5μCi/kg corresponding to 1000 rad. Dose protraction by fractionated application of 224Ra with individual injections of 0.5 or 1.5 or 4.5μCi/kg twice weekly and treatment periods of 4, 12, 24 and 36 weeks reaching total doses of 12μCi/kg (m.s.d. 360 rad), 36μCi/kg (m.s.d. 1080 rad) and 72μCi/kg (m.s.d. 2160 rad) resulted in an increased osteosarcoma incidence with protraction time and total dose. In this series the highest osteosarcoma (more than 90%) was observed after a protraction of 36μCi/kg (m.s.d. 1080 rad) over 36 weeks. After single injection of 224Ra or 227Th in the higher dose range the head bones represented the main location of the osteosarcoma. In addition an increased occurrence of ossifying fibromas of the jaws was observed in the higher dose groups. Fractionated application of 224Rad did not increase the tumor risk of the head bones. After 50μCi/kg of 227Th (m.s.d. 10,000 rad) bone necrosis preceded the appearance of bone tumors. A somewhat earlier occurrence of leukemia was seen in certain groups after single injection of 227Th and one group of fractionated application of 224Ra. AU - Mueller, W.A. AU - Goessner, W. AU - Hug, O. AU - Luz, A. C1 - 40943 C2 - 40383 SP - 33-55 TI - Late effects after incorporation of the short-lived α-emitters 224Ra and 227Th in mice. JO - Health Phys. VL - 35 IS - 1 PY - 1978 SN - 0017-9078 ER - TY - JOUR AB - 224Ra as a short-lived boneseeker is an important substance in medicine as well as in biology. Unsystematic attempts were made a short time after its discovery to introduce 224Ra in therapy. Besides its external application in dermatology the treatment of rheumatic disease by intravenous injection seemed to be promising. From 1944-1952 about 2,000 patients, most of them with tuberculosis or ankylosing spondylitis were treated in a German hospital with repeated intravenous injections of 'Peteosthor', a combination containing 224Ra with traces of platinum and eosin. The patients of this group, among them many children, received injections totalling up to about 4000μCi 224Ra. Following this therapy, different lesions were observed which were suspected to be due to irradiation. These patients are being followed up by Spiess. The treatment of rheumatic diseases, mainly ankylosing spondylitis, by injections of 224Ra has nevertheless continued up to now. More than 1.500 additional patients have been treated in German hospitals. This group, exclusively adults, has received rather low amounts (250-300μCi) of 224R and are now also under study. While in the Spiess series more than 50 bone sarcomas were observed, in the second group among about 600 living and 200 deceased only one sarcoma, a reticulum cell sarcoma of bone marrow, has been observed so far. Based on various linear hypothetical dose-effect relationships in this group an osteosarcoma incidence of 3-5 per 1,000 patients could be expected during the first 20 years following average skeletal doses of 56 rad. The activity applied was expressed in the past in 'electrostatic units'. Retrospective dose calculations make necessary the conversion of this specification to Curie terms. A typical stated activity of 200 e.s.u. for the day of injection corresponds to about 28μCi 224Ra at that time. In experiments started in 1965 in Neuherberg, Germany, the acute and late effects of 224Ra and 227Th in rats and mice are investigated. Similar experiments are under way in Czechoslovakia. In Salt Lake City, Utah, in connection with studies on boneseeking radioisotope using dogs, a pilot study on 224Ra was started in 1963. Together with studies of Ra and Th toxicity a mock dial paint containing 224Ra and 234Th was developed which yielded interesting results for radium metabolism in man. As 224Ra is a 232Th decay product, it might play a certain role in the Thorotrast problem. Further international collaboration in these fields will be necessary in the future to improve knowledge on dose and dose effect. AU - Schales, F. C1 - 40956 C2 - 40364 SP - 25-32 TI - Brief history of 224Ra usage in radiotherapy and radiobiology. JO - Health Phys. VL - 35 IS - 1 PY - 1978 SN - 0017-9078 ER - TY - JOUR AU - Bunzl, K.W. AU - Hoetzl, H. AU - Winkler, R.A. C1 - 40961 C2 - 40362 SP - 87-89 TI - Frequency distribution analysis of the long lived beta activity of air dust. JO - Health Phys. VL - 33 IS - 1 PY - 1977 SN - 0017-9078 ER - TY - JOUR AB - A system of four 5phix5 in. cylindrical NaI (TI) is required for the study of regional deposition and lung clearance of inhaled γ emitting aerosol contaminants. Each of the four detectors is coupled to a collimation system of rectangular opening to achieve uniformity in response across the lung volume. The uniformity in response can be adjusted to any equired degree for the different γ ray energies by displacement of the detectors relative to the fixed collimation system. The parameters of the system are optimized by a computational study based on the theoretical evaluation of detection efficiency and response. The measured response of the system for a 137Cs point source at different positions of the assumed lung model is presented. The detection limits of the system with lead collimators of 4 cm wall thickness range from 6 to 17 nCi depending on photon energy and can be improved by additional shielding. AU - Morsy, S.M. AU - Werner, E.E. AU - Stahlhofen, W. AU - Pohlit, W. C1 - 41364 C2 - 40412 SP - 243-251 TI - A detector of adjustable response for the study of lung clearance. JO - Health Phys. VL - 32 IS - 4 PY - 1977 SN - 0017-9078 ER -