TY - JOUR AB - The most recent publicly available data on all solid cancer incidence from the Life Span Study (LSS) of Japanese A-bomb survivors provides colon dose contributions weighted with a relative biological effectiveness (RBE) of 10 for neutrons, relative to gammas. However, there is evidence from several investigations that the neutron RBE for A-bomb survivors may be higher than 10. The change in the shape of the corresponding dose-response curves was evaluated by Hafner and co-workers in a previous study by applying sex-specific linear-quadratic dose models to previous LSS data for all solid cancer incidence that include separate neutron and gamma absorbed doses for several organs, in contrast to the most recent data. The resulting curvature change became significantly negative for males at an RBE of 140 for colon, 100 for liver, and 80 for organ averaged dose. For females, the corresponding RBE values were 110, 80, and 60 for colon, liver, and organ averaged doses. The present study compares three different methods to calculate the 95% confidence intervals in an analysis of the curvature with increasing RBE. Further, the impact of a higher neutron RBE on the work of the International Commission on Radiological Protection, and the importance of including uncertainties and performing sensitivity analysis of different parameters in radiation risk assessment are discussed. AU - Hafner, L.* AU - Walsh, L.* AU - Rühm, W. C1 - 69034 C2 - 53819 SP - 17-22 TI - Discussion of uncertainties and the impact of different neutron RBEs on all solid cancer radiation incidence risks obtained from the Japanese A-bomb survivor data. JO - Ann. ICRP VL - 52 IS - 1-2 PY - 2023 SN - 0146-6453 ER - TY - JOUR AU - Bolch, W.E.* AU - Eckermann, K.* AU - Endo, A.* AU - Hunt, J.G.S.* AU - Jokisch, D.W.* AU - Kim, C.H.* AU - Kim, K.P.* AU - Lee, C.* AU - Li, J.* AU - Petoussi-Henß, N. AU - Sato, T.* AU - Schlattl, H. AU - Yeom, Y.S.* AU - Zankl, M. C1 - 60283 C2 - 49087 SP - 5-297 TI - Paediatric computational reference phantoms. JO - Ann. ICRP VL - 49 IS - 1 PY - 2020 SN - 0146-6453 ER - TY - JOUR AU - Kim, C.H.* AU - Yeom, Y.S.* AU - Petoussi-Henß, N. AU - Zankl, M. AU - Bolch, W.E.* AU - Lee, C.* AU - Choi, C.* AU - Nguyen, T.T.* AU - Eckerman, K.* AU - Kim, H.S.* AU - Han, M.C.* AU - Qiu, R.* AU - Chung, B.S.* AU - Han, H.* AU - Shin, B.* C1 - 61013 C2 - 49633 SP - 13-201 TI - Adult mesh-type reference computational phantoms. JO - Ann. ICRP VL - 49 IS - 3 PY - 2020 SN - 0146-6453 ER - TY - JOUR AB - This publication presents radionuclide-specific organ and effective dose rate coefficients for members of the public resulting from environmental external exposures to radionuclide emissions of both photons and electrons, calculated using computational phantoms representing the ICRP reference newborn, 1-year-old, 5-year-old, 10-year-old, 15- year-old, and adult males and females. Environmental radiation fields of monoenergetic photon and electron sources were firstly computed using the Monte Carlo radiation transport code PHITS (Particle and Heavy Ion Transport code System) for source geometries representing environmental radionuclide exposures including planar sources on and within the ground at different depths (representing radionuclide ground contamination from fall-out or naturally occurring terrestrial sources), volumetric sources in air (representing a radioactive cloud), and uniformly distributed sources in simulated contaminated water. For the above geometries, the exposed reference individual is considered to be completely within the radiation field. Organ equivalent dose rate coefficients for monoenergetic photons and electrons were next computed employing the PHITS code thus simulating photon and electron interactions within the tissues and organs of the exposed reference individual. For quality assurance purposes, further cross-check calculations were performed using GEANT4, EGSnrc, MCNPX, MCNP6, and the Visible Monte Carlo radiation transport codes. From the monoenergetic values, nuclide-specific effective and organ equivalent dose rate coefficients for several radionuclides for the above environmental exposures were computed using the nuclear decay data from Publication 107. The coefficients are given as dose rates normalised to radionuclide concentrations in environmental media, such as radioactivity concentration, in units of nSv h-1 Bq-1 m-2 or nSv h-1 Bq-1 m-3 and can be re-normalised to ambient dose equivalent (Sv Sv-1) or air kerma (Sv Gy-1). The findings showed that, in general, the smaller the body mass of the phantom, the higher the organ and effective dose due to (1) closer proximity to the source (in the case of ground contamination) and (2) the smaller amount of body shielding of internal organs in the younger and smaller reference phantoms. The difference in effective dose between an adult and an infant is 60-140% at a photon energy of 50 keV, while it is less than 70% above a photon energy of 100 keV, where the smaller differences are observed for air submersion and the largest differences are observed for soil contamination on the surface of the ground. For realistic exposure situations of radionuclide environmental contamination, the difference was found to be more moderate. For example, for radioactive caesium (134Cs, 136Cs, 137Cs/137mBa) deposited on and in the ground, the difference in effective dose between an adult and an infant was in the range of 20-60%, depending on the radioactivity deposition depth within the soil. ICRP routinely solicits comments on most draft documents prior to publication, with the exception of those that are basically compilations of computed values such as specific absorbed fraction values or dose conversion factors.View comments Draft Document AU - Petoussi-Henß, N. AU - Satoh, D.* AU - Endo, A.* AU - Eckerman, K.F.* AU - Bolch, W.E.* AU - Hunt, J.* AU - Jansen, J.T.M.* AU - Kim, C.H.* AU - Lee, C.* AU - Saito, K.* AU - Schlattl, H. AU - Yeom, Y.S.* AU - Yoo, S.J.* C1 - 59439 C2 - 48813 SP - 11-145 TI - Dose coefficients for external exposures to environmental sources. JO - Ann. ICRP VL - 49 IS - 2 PY - 2020 SN - 0146-6453 ER - TY - JOUR AB - The concept of lifetime radiation risk of stochastic detrimental health outcomes is important in contemporary radiation protection, being used either to calculate detriment-weighted effective dose or to express risks following radiation accidents or medical uses of radiation. The conventionally applied time-integrated risks of radiation exposure are computed using average values of current population and health statistical data that need to be projected far into the future. By definition, the lifetime attributable risk (AR) is an approximation to more general lifetime risk quantities and is only valid for exposures under 1 Gy. The more general quantities, such as excess lifetime risk (ELR) and risk of exposure-induced cancer, are free of dose range constraints, but rely on assumptions concerning the unknown total radiation effect on demographic and health statistical data, and are more computationally complex than AR. Consideration of highly uncertain competing risks for other radiation-attributed outcomes are required in appropriate assessments of time-integrated risks of specific outcomes following high-dose (>1 Gy) exposures, causing non-linear dose responses in the resulting ELR estimate. Being based on the current population and health statistical data, the conventionally applied time-integrated risks of radiation exposure are: (i) not well suited for projections many years into the future because of the large uncertainties in future secular trends in the population-specific disease rates; and (ii) not optimal for application to atypical groups of exposed persons not well represented by the general population. Specifically, medical patients are atypical in this respect because their prospective risks depend strongly on the original diagnosis, the treatment modality, general cure rates, individual radiation sensitivity, and genetic predisposition. Another situation challenging the application of conventional risk quantities is a projection of occupational radiation risks associated with space flight, both due to higher radiation doses and astronauts’ generally excellent health condition due to pre-selection, training, and intensive medical screening. An alternative quantity, named ‘radiation-attributed decrease of survival’ (RADS), known in past general statistical literature as ‘cumulative risk’, is recommended here for applications in space and medicine to represent the cumulative radiation risk conditional on survival until a certain age. RADS is only based on the radiation-attributed hazard rendering an insensitivity to competing risks or projections of current population statistics far into the future. Therefore, RADS is highly suitable for assessing semi-personalised radiation risks after radiation exposures from space missions or medical applications of radiation. AU - Ulanowski, A. AU - Kaiser, J.C. AU - Schneider, U.* AU - Walsh, L.* C1 - 60312 C2 - 49379 SP - 200-212 TI - Lifetime radiation risk of stochastic effects – prospective evaluation for space flight or medicine. JO - Ann. ICRP VL - 49 PY - 2020 SN - 0146-6453 ER - TY - JOUR AB - European Radiation Dosimetry Group (EURADOS) Working Group 7 is a network on internal dosimetry that brings together researchers from more than 60 institutions in 21 countries. The work of the group is organised into task groups that focus on different aspects, such as development and implementation of biokinetic models (e.g. for diethylenetriamine penta-acetic acid decorporation therapy), individual monitoring and the dose assessment process, Monte Carlo simulations for internal dosimetry, uncertainties in internal dosimetry, and internal microdosimetry. Several intercomparison exercises and training courses have been organised. The IDEAS guidelines, which describe - based on the International Commission on Radiological Protection's (ICRP) biokinetic models and dose coefficients - a structured approach to the assessment of internal doses from monitoring data, are maintained and updated by the group. In addition, Technical Recommendations for Monitoring Individuals for Occupational Intakes of Radionuclides have been elaborated on behalf of the European Commission, DG-ENER (TECHREC Project, 2014-2016, coordinated by EURADOS). Quality assurance of the ICRP biokinetic models by calculation of retention and excretion functions for different scenarios has been performed and feedback was provided to ICRP. An uncertainty study of the recent caesium biokinetic model quantified the overall uncertainties, and identified the sensitive parameters of the model. A report with guidance on the application of ICRP biokinetic models and dose coefficients is being drafted at present. These and other examples of the group's activities, which complement the work of ICRP, are presented. AU - Breustedt, B.* AU - Blanchardon, E.* AU - Castellani, C.M.* AU - Etherington, G.* AU - Franck, D.* AU - Giussani, A.* AU - Hofmann, W.* AU - Lebacq, A.L.* AU - Li, W. AU - Noßke, D.* AU - López, M.A.* C1 - 53416 C2 - 44787 TI - EURADOS work on internal dosimetry. JO - Ann. ICRP PY - 2018 SN - 0146-6453 ER - TY - JOUR AB - Committee 2 of the International Commission on Radiological Protection (ICRP) has constructed mesh-type adult reference computational phantoms by converting the voxel-type ICRP Publication 110 adult reference computational phantoms to a high-quality mesh format, and adding those tissues that were below the image resolution of the voxel phantoms and therefore not included in the Publication 110 phantoms. The new mesh phantoms include all the necessary source and target tissues for effective dose calculations, including the 8-40-µm-thick target layers of the alimentary and respiratory tract organs, thereby obviating the need for supplemental organ-specific stylised models (e.g. respiratory airways, alimentary tract organ walls and stem cell layers, lens of the eye, and skin basal layer). To see the impact of the new mesh-type reference phantoms, dose coefficients for some selected external and internal exposures were calculated and compared with the current reference values in ICRP Publications 116 and 133, which were calculated by employing the Publication 110 phantoms and the supplemental stylised models. The new mesh phantoms were also used to calculate dose coefficients for industrial radiography sources near the body, which can be used to estimate the organ doses of the worker who is accidentally exposed by an industrial radiography source; in these calculations, the mesh phantoms were deformed to reflect the size of the worker, and also to evaluate the effect of posture on dose coefficients. AU - Kim, C.H.* AU - Yeom, Y.S.* AU - Nguyen, T.T.* AU - Han, M.C.* AU - Choi, C.* AU - Lee, H.* AU - Han, H.B.* AU - Shin, B.* AU - Lee, J.K.* AU - Kim, H.S.* AU - Zankl, M. AU - Petoussi-Henß, N. AU - Bolch, W.E.* AU - Lee, C.* AU - Chung, B.S.* AU - Qiu, R.* AU - Eckerman, K.F.* C1 - 53398 C2 - 44847 SP - 146645318756231 TI - New mesh-type phantoms and their dosimetric applications, including emergencies. JO - Ann. ICRP PY - 2018 SN - 0146-6453 ER - TY - BOOK AB - The aim of the International Commission on Radiological Protection (ICRP) is to protect humans against cancer and other diseases and effects associated with exposure to ionising radiation, and also to protect the environment, without unduly limiting the beneficial use of ionising radiation. As of the second half of 2017, four committees are contributing to the overall mission of ICRP, including Committee 1 (Radiation Effects). The role of Committee 1 includes consideration of the risks and mechanisms of induction of cancer and heritable disease; discussion of the risks, severity, and mechanisms of induction of tissue/organ damage and developmental defects; and review of the effects of ionising radiation on non-human biota at population level. This paper gives an overview of the recent activities of Committee 1, and discusses the focus of its active task groups. AU - Rühm, W. AU - Ban, N.* AU - Tirmarche, M.* C1 - 52438 C2 - 43973 TI - The mandate and work of ICRP Committee 1 on radiation effects. JO - Ann. ICRP VL - 1 PY - 2018 SN - 0146-6453 ER - TY - JOUR AB - Since the early 1980s, the European Radiation Dosimetry Group (EURADOS) has been maintaining a network of institutions interested in the dosimetry of ionising radiation. As of 2017, this network includes more than 70 institutions (research centres, dosimetry services, university institutes, etc.), and the EURADOS database lists more than 500 scientists who contribute to the EURADOS mission, which is to promote research and technical development in dosimetry and its implementation into practice, and to contribute to harmonisation of dosimetry in Europe and its conformance with international practices. The EURADOS working programme is organised into eight working groups dealing with environmental, computational, internal, and retrospective dosimetry; dosimetry in medical imaging; dosimetry in radiotherapy; dosimetry in high-energy radiation fields; and harmonisation of individual monitoring. Results are published as freely available EURADOS reports and in the peer-reviewed scientific literature. Moreover, EURADOS organises winter schools and training courses on various aspects relevant for radiation dosimetry, and formulates the strategic research needs in dosimetry important for Europe. This paper gives an overview on the most important EURADOS activities. More details can be found at www.eurados.org . AU - Rühm, W. AU - Bottollier-Depois, J.F.* AU - Gilvin, P.* AU - Harrison, R.* AU - Knežević, Z.* AU - Lopez, M.A.* AU - Tanner, R.* AU - Vargas, A.* AU - Woda, C. C1 - 53415 C2 - 44858 SP - 146645318756224 TI - The work programme of EURADOS on internal and external dosimetry. JO - Ann. ICRP VL - 47 IS - 3-4 PY - 2018 SN - 0146-6453 ER - TY - JOUR AB - Phantoms simulating the human body play a central role in radiation dosimetry. The first computational body phantoms were based upon mathematical expressions describing idealised body organs. With the advent of more powerful computers in the 1980s, voxel phantoms have been developed. Being based on three-dimensional images of individuals, they offer a more realistic anatomy. Hence, the International Commission on Radiological Protection (ICRP) decided to construct voxel phantoms representative of the adult Reference Male and Reference Female for the update of organ dose coefficients. Further work on phantom development has focused on phantoms that combine the realism of patient-based voxel phantoms with the flexibility of mathematical phantoms, so-called 'boundary representation' (BREP) phantoms. This phantom type has been chosen for the ICRP family of paediatric reference phantoms. Due to the limited voxel resolution of the adult reference computational phantoms, smaller tissues, such as the lens of the eye, skin, and micron-thick target tissues in the respiratory and alimentary tract regions, could not be segmented properly. In this context, ICRP Committee 2 initiated a research project with the goal of producing replicas of the ICRP Publication 110 phantoms in polygon mesh format, including all source and target regions, even those with micron resolution. BREP phantoms of the fetus and the pregnant female at various stages of gestation complete the phantoms available for radiation protection computations. AU - Zankl, M. AU - Becker, J. AU - Lee, C.* AU - Bolch, W.E.* AU - Yeom, Y.S.* AU - Kim, C.H.* C1 - 53397 C2 - 44848 SP - 146645318756229 TI - Computational phantoms, ICRP/ICRU, and further developments. JO - Ann. ICRP VL - 1 PY - 2018 SN - 0146-6453 ER - TY - JOUR AU - Ulanowski, A. AU - Copplestone, D.* AU - Batlle, J.V.I.* C1 - 52771 C2 - 44148 SP - 1-136 TI - Dose coefficients for non-human biota environmentally exposed to radiation. JO - Ann. ICRP VL - 46 IS - 2 PY - 2017 SN - 0146-6453 ER - TY - JOUR AB - Major current efforts within Committee 2 of the International Commission on Radiological Protection (ICRP) involve the development of dose coefficients for inhalation and ingestion of radionuclides, and those for exposure to environmental radiation fields. These efforts build upon changes in radiation and tissue weighting factors (Publication 103), radionuclide decay schemes (Publication 107), computational phantoms of the adult reference male and female (Publication 110), external dose coefficients for adult reference workers for idealised radiation fields (Publication 116), models of radionuclide intake (Publications 66,100and130), and models of radionuclide systemic biokinetics (Publication 130). This paper will review the overall computational framework for both internal and external dose coefficients. For internal exposures, the work entails assessment of organ self-dose and cross-dose from monoenergetic particle emissions (specific absorbed fraction), absorbed dose per nuclear transformation (S value), time-integrated activity of the radionuclide in source tissues (inhalation, ingestion, and systemic biokinetic models), and their numerical combination to yield the organ equivalent dose or effective dose per activity inhaled or ingested. Various challenges are reviewed that were not included in the development ofPublication 30dose coefficients, which were based upon much more simplified biokinetic models and computational phantoms. For external exposures, the computations entail the characterisation of environmental radionuclide distributions, the transport of radiation particles through that environment, and the tracking of energy deposition to the organs of the exposed individual. Progress towards the development of dose coefficients to members of the general public (adolescents, children, infants and fetuses) are also reviewed. AU - Bolch, W.E.* AU - Petoussi-Henß, N. AU - Paquet, F.* AU - Harrison, J.D.* C1 - 48264 C2 - 41004 SP - 156-177 TI - ICRP dose coefficients: Computational development and current status. JO - Ann. ICRP VL - 45 PY - 2016 SN - 0146-6453 ER - TY - JOUR AB - Dose coefficients for assessment of internal exposures to radionuclides are radiological protection quantities giving either the organ equivalent dose or effective dose per intake of radionuclide following ingestion or inhalation. In the International Commission on Radiological Protection’s (ICRP) Occupational Intakes of Radionuclides (OIR) publication series, new biokinetic models for distribution of internalised radionuclides in the human body are presented as needed for establishing time-integrated activity within organs of deposition (source regions). This series of publications replaces Publications 30 and 68 (ICRP, 1979, 1980, 1981, 1988, 1994b). In addition, other fundamental data needed for computation of the dose coefficients are radionuclide decay data (energies and yields of emitted radiations), which are given in Publication 107 (ICRP, 2008), and specific absorbed fraction (SAF) values – defined as the fraction of the particle energy emitted in a source tissue region that is deposited in a target tissue region per mass of target tissue. This publication provides the technical basis for SAFs relevant to internalised radionuclide activity in the organs of Reference Adult Male and Reference Adult Female as defined in Publications 89 and 110 (ICRP, 2002, 2009). SAFs are given for uniform distributions of mono-energetic photons, electrons, alpha particles, and fission-spectrum neutrons over a range of relevant energies. Electron SAFs include both collision and radiative components of energy deposition. SAF data are matched to source and target organs of the biokinetic models of the OIR publication series, as well as the Publication 100 (ICRP, 2006) Human Alimentary Tract Model and the Publication 66 (ICRP, 1994a) Human Respiratory Tract Model, the latter as revised within Publication 130 (ICRP, 2015). This publica- tion further outlines the computational methodology and nomenclature for assess- ment of internal dose in a manner consistent with that used for nuclear medicine applications. Numerical data for particle-specific and energy-dependent SAFs are given in electronic format for numerical coupling to the respiratory tract, alimentary tract, and systemic biokinetic models of the OIR publication series. AU - Bolch, W.E.* AU - Jokisch, D.W.* AU - Zankl, M. AU - Eckerman, K.F.* AU - Fell, T.* AU - Manger, R.* AU - Endo, A.* AU - Hunt, J.* AU - Kim, K.P.* AU - Petoussi-Henß, N. C1 - 50019 C2 - 41969 SP - 1-74 TI - The ICRP computational framework for internal dose assessment for reference adults: Specific absorbed fractions. JO - Ann. ICRP VL - 45 IS - 2 PY - 2016 SN - 0146-6453 ER - TY - JOUR AB - The International Commission on Radiological Protection (ICRP) reference male and female adult phantoms, described in Publication 110, are voxel phantoms based on whole-body computed tomography scans of a male and a female patient, respectively. The voxel in-plane resolution and the slice thickness, of the order of a few millimetres, are insufficient for proper segmentation of smaller tissues such as the lens of the eye, the skin, and the walls of some organs. The calculated doses for these tissues therefore present some limitations, particularly for weakly penetrating radiation. Similarly, the Publication 110 phantoms cannot represent 8-40-µm-thick target regions in respiratory or alimentary tract organs. Separate stylised models have been used to represent these tissues for calculation of the ICRP reference dose coefficients (DCs). ICRP Committee 2 recently initiated a research project, the ultimate goal of which is to convert the Publication 110 phantoms to a high-quality polygon-mesh (PM) format, including all source and target regions, even those of the 8-40-µm-thick alimentary and respiratory tract organs. It is expected that the converted phantoms would lead to the same or very similar DCs as the Publication 110 reference phantoms for penetrating radiation and, at the same time, provide more accurate DCs for weakly penetrating radiation and small tissues. Additionally, the reference phantoms in the PM format would be easily deformable and, as such, could serve as a starting point to create phantoms of various postures for use, for example, in accidental dose calculations. This paper will discuss the current progress of the phantom conversion project and its significance for ICRP DC calculations. AU - Kim, C.H.* AU - Yeom, Y.S.* AU - Nguyen, T.T.* AU - Wang, Z.J.* AU - Kim, H.S.* AU - Han, M.C.* AU - Lee, J.K.* AU - Zankl, M. AU - Petoussi-Henß, N. AU - Bolch, W.E.* AU - Lee, C.* AU - Chung, B.S.* C1 - 48094 C2 - 39892 SP - 188-201 TI - The reference phantoms: Voxel vs polygon. JO - Ann. ICRP VL - 45 PY - 2016 SN - 0146-6453 ER - TY - JOUR AB - Quantification of biological effects (cancer, other diseases, and cell damage) associated with exposure to ionising radiation has been a major issue for the International Commission on Radiological Protection (ICRP) since its foundation in 1928. While there is a wealth of information on the effects on human health for whole-body doses above approximately 100 mGy, the effects associated with doses below 100 mGy are still being investigated and debated intensively. The current radiological protection approach, proposed by ICRP for workers and the public, is largely based on risks obtained from high-dose and high-dose-rate studies, such as the Japanese Life Span Study on atomic bomb survivors. The risk coefficients obtained from these studies can be reduced by the dose and dose-rate effectiveness factor (DDREF) to account for the assumed lower effectiveness of low-dose and low-dose-rate exposures. The 2007 ICRP Recommendations continue to propose a value of 2 for DDREF, while other international organisations suggest either application of different values or abandonment of the factor. This paper summarises the current status of discussions, and highlights issues that are relevant to reassessing the magnitude and application of DDREF. AU - Rühm, W. AU - Azizova, T.V.* AU - Bouffler, S.D.* AU - Little, M.P.* AU - Shore, R.E.* AU - Walsh, L.* AU - Woloschak, G.E.* C1 - 48083 C2 - 39899 SP - 262-279 TI - Dose-rate effects in radiation biology and radiation protection. JO - Ann. ICRP VL - 45 PY - 2016 SN - 0146-6453 ER - TY - JOUR AB - Diversity of living organisms and their environmental radiation exposure conditions represents a special challenge for non-human dosimetry. In order to contend with such diversity, the International Commission on Radiological Protection (ICRP) has: (a) set up points of reference by providing dose conversion coefficients (DCCs) for reference entities known as 'Reference Animals and Plants' (RAPs); and (b) used dosimetric models that pragmatically assume simple body shapes with uniform composition and density, homogeneous internal contamination, a limited set of idealised external radiation sources, and truncation of the radioactive decay chains. This pragmatic methodology has been further developed and extended systematically. Significant methodological changes include: a new extended approach for assessing doses of external exposure for terrestrial animals, transition to the contemporary ICRP radionuclide database, assessment-specific consideration of the contribution of radioactive progeny to dose coefficients of parent nuclides, and the use of generalised allometric relationships in the estimation of biokinetic or metabolic parameters. The new methodological developments resulted in a revision of the DCCs for RAPs. Tables of the dose coefficients have now been complemented by a web-based software tool, which can be used to calculate a user-specific DCC for an organism of arbitrary mass and shape, located at user-defined height above the ground, and for an arbitrary radionuclide and its radioactive progeny. AU - Ulanowski, A. C1 - 48146 C2 - 39954 SP - 225-238 TI - Dosimetry for animals and plants: Contending with biota diversity. JO - Ann. ICRP VL - 45 PY - 2016 SN - 0146-6453 ER - TY - JOUR AB - Based upon recent epidemiological studies of ocular exposure, the Main Commission of the International Commission on Radiological Protection (ICRP) in ICRP Publication 118 states that the threshold dose for radiation-induced cataracts is now considered to be approximately 0.5 Gy for both acute and fractionated exposures. Consequently, a reduction was also recommended for the occupational annual equivalent dose to the lens of the eye from 150 mSv to 20 mSv, averaged over defined periods of 5 years. To support ocular dose assessment and optimisation, Committee 2 included Annex F within ICRP Publication 116. Annex F provides dose coefficients - absorbed dose per particle fluence - for photon, electron, and neutron irradiation of the eye and lens of the eye using two dosimetric models. The first approach uses the reference adult male and female voxel phantoms of ICRP Publication 110. The second approach uses the stylised eye model of Behrens et al., which itself is based on ocular dimensional data given in Charles and Brown. This article will review the data and models of Annex F with particular emphasis on how these models treat tissue regions thought to be associated with stem cells at risk. AU - Bolch, W.E.* AU - Dietze, G.* AU - Petoussi-Henß, N. AU - Zankl, M. C1 - 44078 C2 - 36788 SP - 91-111 TI - Dosimetric models of the eye and lens of the eye and their use in assessing dose coefficients for ocular exposures. JO - Ann. ICRP VL - 44 IS - 1 PY - 2015 SN - 0146-6453 ER - TY - JOUR AB - The enormous diversity of non-human biota is a specific challenge when developing and applying dosimetric models for assessing exposures to flora and fauna from environmental radioactivity. Dosimetric models, adopted by the International Commission on Radiological Protection (ICRP), provide dose conversion coefficients for a large variety of biota, including the Reference Animals and Plants. The models use a number of simplified approaches, often ignoring presumably insignificant details. Simple body shapes with uniform composition and density, homogeneous internal contamination, a limited set of external radiation sources for terrestrial animals and plants, and truncation of radioactive decay chains are a few examples of simplifying assumptions underlying the dose conversion coefficients included in ICRP Publication 108. However, many specific assessment tasks require dosimetric data for non-standard species or irradiation scenarios. The further development of dosimetric models aims at the implementation of flexible choices of animals and plants, as well as of their irradiation conditions (e.g. trees); more systematic consideration of internal exposures from radionuclides concentrated in specific organs; and task-oriented choice of decay chains based on ICRP Publication 107. An extensive set of non-human dosimetric data might require specific software to facilitate fast, accurate, and flexible selection of pertinent dose conversion coefficients for specific assessment tasks. AU - Ulanowski, A. AU - Pröhl, G.* C1 - 10845 C2 - 30492 SP - 218-232 TI - Dosimetry for reference animals and plants: Current state and prospects. JO - Ann. ICRP VL - 41 IS - 3-4 PB - Elsevier PY - 2012 SN - 0146-6453 ER - TY - JOUR AU - Petoussi-Henß, N. AU - Bolch, W.E.* AU - Eckerman, K.F.* AU - Endo, A. AU - Hertel, N.* AU - Hunt, J.* AU - Pelliccioni, M.* AU - Schlattl, H. AU - Zankl, M. AU - International Commission on Radiological Protection (*) AU - International Commission on Radiation Units and Measurements (*) A2 - Clement, C.H.* C1 - 8688 C2 - 29898 CY - Ottawa SP - 257 S. TI - Conversion coefficients for radiological protection quantities for external radiation exposures. JO - Ann. ICRP VL - 40 IS - 2-5 PB - Elsevier PY - 2010 SN - 0146-6453 ER - TY - JOUR AU - Holm, L.-E. AU - Clark, M.E. AU - Gentner, N. AU - Larsson, C.-M. AU - Pentreath, R.J. AU - Alexakhin, R. AU - Brechignac, F. AU - Carroll, S. AU - Fujimoto, K. AU - Loy, J. AU - Pröhl, G. AU - Robinson, C. AU - Shpyth, A. AU - Strand, P. AU - Tsela, A. AU - Woodhead, D.S. AU - Xuan, Y. A2 - Clement, C.H.* C1 - 1417 C2 - 26789 CY - Oxford, UK SP - 330 S. TI - Environmental protection: The concept and use of reference animals and plant. JO - Ann. ICRP VL - 108 PB - Elsevier PY - 2009 SN - 0146-6453 ER - TY - JOUR AU - Zankl, M. AU - Eckermann, K.F.* AU - Petoussi-Henß, N. AU - Bolch, W.E. AU - Menzel, H.G.* A2 - Valentin, J.* C1 - 1839 C2 - 26788 CY - Amsterdam SP - 165 S. TI - Adult reference computational phantoms. JO - Ann. ICRP VL - 110 PB - Elsevier PY - 2009 SN - 0146-6453 ER - TY - JOUR AU - Drexler, G. C1 - 19580 C2 - 12683 SP - 41 S. TI - Annual Limits on Intake of Radionuclides by Workers Based on the 1990 Recommendations. JO - Ann. ICRP VL - 21 PY - 1991 SN - 0146-6453 ER - TY - JOUR AU - Drexler, G. C1 - 17459 C2 - 10363 SP - 132 S. TI - Data for Use in Protection Against External Radiation. JO - Ann. ICRP VL - 17 PY - 1987 SN - 0146-6453 ER -