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The purpose of this Publication is to provide guidance on radiological protection in industries involving NORM. These industries may give rise to multiple hazards and the radiological hazard is not necessarily dominant. The industries are diverse and may involve exposure to people and the environment where protective actions need to be considered. In some cases, there is a potential for significant routine exposure to workers and members of the public if suitable control measures are not considered.
Following the issuance of new radiological protection recommendations in Publication 103 (ICRP, 2007), the Commission released, in Publication 110 (ICRP, 2009), the adult male and female voxel-type reference computational phantoms to be used for the calculation of the reference dose coefficients for both external and internal exposures. While providing more anatomically realistic representations of internal anatomy than the older stylised phantoms, the voxel phantoms have their limitations, mainly due to voxel resolution, especially with respect to small tissue structures (e.g. lens of the eye) and very thin tissue layers (e.g. stem cell layers in the stomach wall mucosa and intestinal epithelium). This report describes the construction of the adult mesh-type reference computational phantoms (MRCPs) that are the modelling counterparts of the Publication 110 voxel-type reference computational phantoms. The MRCPs include all source and target regions needed for estimating effective dose, even the m-thick target regions in the respiratory and alimentary tract, skin, and urinary bladder, assimilating the supplemental stylised models. The MRCPs can be directly implemented into Monte Carlo particle transport codes for dose calculations, i.e. without voxelisation, fully maintaining the advantages of the mesh geometry.
The International Commission on Radiological Protection (ICRP) has developed and systematically updated the system of radiological protection, which now recommends optimisation of protection measures within or guided by appropriate restrictions, such as dose constraints or reference levels, in all circumstances. This applies to all exposure situations (planned, emergency and existing) and all categories of exposure (occupational, medical, and public). Optimisation of protection is intended to reduce exposures to levels that are as low as reasonably achievable, economic and societal considerations being taken into account, and to manage medical exposures commensurate with the medical purpose.
In this report the Commission describes its framework for protection of the environment and how it should be applied within the Commission's system of protection. The report expands upon its objectives in relation to protection of the environment and explains the different types of exposure situations to which its recommendations apply. Further recommendations are made with regard to how the Commission's recommendations can be implemented to satisfy different forms of environmental protection objectives and additional information is also given with regard to, in particular, communication with other interested parties and stakeholders. Issues that may arise in relation to compliance are also discussed and a final chapter discusses the overall implications of the Commission's work in this area to date. Appendices 1 and 2 provide some numerical information relating to the Reference Animals and Plants. An Annex to this report considers some of existing types of environmental protection legislation currently in place in relation to large industrial sites and practices, and the various ways in which wildlife are protected from various threats arising from such sites.
This report describes the development and intended use of a series of ten computational phantoms representing the reference male and female at newborn, 1-year-old, 5-year-old, 10-year-old, and 15-year-old as defined in Publication 89. These phantoms have been formally adopted by the ICRP for use within ICRP Committee 2 in the development of age-dependent dose coefficients following the 2007 Recommendations. They are presented in this report in the very same voxelised structures and tissue ID numbers as given in Publication 110 for the adult reference computational phantoms. These paediatric phantoms have been used by Task Group 90 of ICRP Committee 2 in the development of age-dependent dose coefficients representing external exposures to contaminated air, water, and soil. They have also been used by Task Group 96 of ICRP Committee 2 in the development of age-dependent specific absorbed fractions for internally emitted photons, electrons, alpha particles, and neutrons, in a manner similar to the adult SAF (Specific Absorbed Fraction) values given in Publication 133.
For its 4th International Symposium on the System of Radiological Protection, ICRP joined forces with the 2nd European Radiological Protection Research Week (ERPW), to collaborate closely with the five European research platforms: ALLIANCE, EURADOS, EURAMED, MELODI, and NERIS. ICRP-ERPW 2017 attracted more than 500 participants from 42 countries.
The Second ICRP Symposium on the International System of Radiological Protection was held in Abu Dhabi in the UAE on October 22-24, 2013. There were nearly 300 registered participants from 37. The papers in this publication represent a cross-section of the subjects presented during ICRP 2013. In addition to a session providing an overview of the work of ICRP, five topical sessions were held on high-priority issues in radiological protection: tissue reactions, advances in recovery preparedness and response following Fukushima, NORM issues in the real world, the role of the ICRP in medicine and work being carried out by the ICRP on environmental radiation protection. These papers are not recommendations of ICRP and do not necessarily represent the views of ICRP; they are the work of the individual authors. This publication was supported by the German Federal Ministry of Environment, Nature Conservation and Nuclear Safety.
This report provides a review of early and late effects of radiation in normal tissues and organs with respect to radiation protection. It was instigated following a recommendation in ICRP Publication 103 (2007), and it provides updated estimates of 'practical' threshold doses for tissue injury defined at the level of 1% incidence. Estimates are given for morbidity and mortality endpoints in all organ systems following acute, fractionated, or chronic exposure. The organ systems comprise the haematopoietic, immune, reproductive, circulatory, respiratory, musculoskeletal, endocrine, and nervous systems; the digestive and urinary tracts; the skin; and the eye.
Recent epidemiological studies of the association between lung cancer and exposure to radon and its decay products are reviewed. Particular emphasis is given to pooled case-control studies of residential exposures and to cohorts of underground miners exposed to relatively low levels of radon. The residential and miner epidemiological studies provide consistent estimates of lung cancer risk with statistically significant associations observed at average annual concentrations of about 200 Bq m-3 and cumulative occupational levels of about 50 WLM, respectively. Based on recent results from combined analyses of epidemiological studies of miners, a lifetime excess absolute risk of 5 x 10-4 per WLM (14 x 10-5 per mJ h m-3) should now be used as the nominal probability coefficient for radon and radon progeny induced lung cancer, replacing the previous ICRP Publication 65 value of 2.8 x 10-4 per WLM (8 x 10-5 per mJ h m-3). Current knowledge of radon associated risks for organs other than the lungs does not justify the selection of a detriment coefficient different from the fatality coefficient for radon-induced lung cancer.
Lessons from accidental exposures are, therefore, an invaluable resource for revealing vulnerable aspects of the practice of radiotherapy, and for providing guidance for the prevention of future occurrences. These lessons have successfully been applied to avoid catastrophic events with conventional technologies and techniques. Recommendations, for example, include the independent verification of beam calibration and independent calculation of the treatment times and monitor units for external beam radiotherapy, and the monitoring of patients and their clothes immediately after brachytherapy. New technologies are meant to bring substantial improvement to radiation therapy. However, this is often achieved with a considerable increase in complexity, which in turn brings opportunities for new types of human error and problems with equipment. Dissemination of information on these errors or mistakes as soon as it becomes available is crucial in radiation therapy with new technologies. In addition, information on circumstances that almost resulted in serious consequences (near misses) is also important, as the same type of events may occur elsewhere. Sharing information about near-misses is thus a complementary important aspect of prevention. Lessons from retrospective information are provided in Sections 2 and 4 of this report.
This report was prepared to provide advice on the application of the Commission's 2007 Recommendations. The advice includes the preparedness for, and response to, all radiation emergency exposure situations defined as: 'situations that may occur during the operation of a planned situation, or from a malicious act, or from any other unexpected situation and require urgent action in order to avoid or reduce undesirable consequences'. An emergency exposure situation may evolve, in time, into an existing exposure situation. The Commission's advice for these types of situation is published in two complementary documents (that for emergency exposure situations in this report, that for existing exposure situations following emergency exposure situations in a forthcoming report entitled 'Application of the Commission's recommendations to the protection of individuals living in long-term contaminated territories after a nuclear accident or a radiation emergency').
This publication reviews what is known about the effects of radiation upon such biotic types (or of similar organisms, where more precise data are lacking) with regard to the effects of mortality, morbidity, reduced reproductive success, and chromosomal damage. Drawing on this information, the report derives a set of derived consideration reference levels for each biotic type in order to help optimise the level of effort that might be expended on its environmental protection, or that of similar types of organisms, and thus serve as points of reference in any wider consideration of what authorities may wish to do under different exposure situations. The various factors that should be taken into account when considering what to do if the derived consideration reference levels are likely to be attained are also discussed. Some broader background information on the types of animals and plants used is also given. Additional information is provided on advice with regard to extrapolating and interpolating the limited set of dosimetric models to other shapes and sizes of animals and plants.
This report explains the process of estimating annual dose and recognises that a number of different methods are available for this purpose. These methods range from deterministic calculations to more complex probabilistic techniques. In addition, a mixture of these techniques may be applied. In selecting characteristics of the representative person, three important concepts should be borne in mind: reasonableness, sustainability, and homogeneity. Each concept is explained and examples are provided to illustrate their roles. Doses to the public are prospective (may occur in the future) or retrospective (occurred in the past). Prospective doses are for hypothetical individuals who may or may not exist in the future, while retrospective doses are generally calculated for specific individuals.
This report presents detailed information on age- and
gender-related differences in the anatomical and physiological
characteristics of reference individuals. These reference values
provide needed input to prospective dosimetry calculations for
radiation protection purposes for both workers and members of the
general public.
Radiopharmaceuticals are increasingly used for the treatment of various cancers with novel radionuclides, compounds, tracer molecules, and administration techniques. The goal of radiation therapy, including therapy with radiopharmaceuticals, is to optimise the relationship between tumour control probability and potential complications in normal organs and tissues. This report provides an overview of therapy procedures and a framework for calculating radiation doses for various treatment approaches.
ICRP Publication 78 replaces the previous ICRP Publication 54 on individual monitoring programmes and the interpretation of results of measurements for intakes of radionuclides by workers. The updating was considered necessary because ICRP published new dose coefficients for intakes of radionuclides by workers in 1994 (ICRP Publication 68). Those new dose coefficients were based on the most recent general recommendations of the Commission (ICRP Publication 60). The present report uses this new information and takes account of the new principles for the radiological protection of workers provided inICRP Publication 75. Thus, the report uses the revised models and the new dose coefficients to give guidance on monitoring programmes and interpretation of results for selected radionuclides of importance in occupational exposure.
The purpose of ICRP 72 is to summarise data on age dependent committed effective dose coefficients for members of the public from intakes by ingestion and inhalation of radioisotopes of the 91 elements described in ICRP Publications 56, 67, 68, 69 and 71. These dose coefficients have been adopted in the International Atomic Energy Agency in their publication on International Basic Safety Standards for Protection against Ionising Radiation, and in the Euratom Directive. The report does not give committed equivalent dose coefficients to tissues and organs. The report will be useful to operational health physicists and to regulatory and advisory bodies responsible for radiation protection.
An ongoing objective of ICRP is to evaluate dose coefficients (doses per unit intake) for members of the public. The purpose ofICRP Publication 71 is to provide updated inhalation dose coefficients for selected radioisotopes of hydrogen, carbon, sulphur, calcium, iron, cobalt, nickel, zinc, selenium, strontium, zirconium, niobium, molybdenum, technetium, ruthenium, silver, antimony, tellurium, iodine, caesium, barium, cerium, lead, polonium, radium, thorium, uranium, neptunium, plutonium, americium and curium. Age-dependent biokinetic models for calcium, curium and for decay products formed following the intake of lead, radium, tellurium, thorium and uranium are provided in annexes.
The Commission's 1990 recommendations on radiation protection standards in 'ICRP Publication 60' were developed to take into account new biological information related to the detriment associated with radiation exposures and supersede the earlier recommendations in 'ICRP Publication 26'. In order to permit immediate application of these new recommendations, revised values of the Annual Limits on Intake (ALIs) based on the methodology and biokinetic information and incorporating the new dose limits and tissue weighting factors, wT were issued as 'ICRP Publication 61'. Since issuing 'ICRP Publication 61', ICRP has published a revised kinetic and dosimetric model of the respiratory tract. The main aim of the present report is to give values of dose coefficients for workers using this new model.
In March 1987 the International Commission on Radiological Protection established a Task Group of Committee 2 "to evaluate dose per unit intake for members of the public". In this, the second of two reports given by the Task Group, ingestion dose coefficients are given for isotopes of sulphur, cobalt, nickel, zinc, molybdenum, technetium, silver, tellurium and polonium using the new tissue weighting factors (wT) given by the Commission in its 1990 Recommendations. Revised ingestion dose coefficients are also included for the radioisotopes given in Part 1 using the new wT values. In addition, ingestion dose coefficients are given for further radioisotopes. A generic model for the biokinetics of lead and the alkaline earths strontium, barium and radium has been introduced for calculating ingestion dose coefficients for radioisotopes of these elements. This model has been applied to the recalculation of the ingestion dose coefficients for Sr-90, the only strontium isotope considered in Part 1. The ICRP has now given new wT values for the urinary bladder and colon, and new information has become available on the biokinetics of plutonium, americium and neptunium in humans. As a result the Task Group considered it appropriate to revise the biokinetic models for these elements given in Part 1.
The International Commission on Radiological Protection issued its last basic recommendations in 1977. The recommendations have been used widely throughout the world to limit exposure of both radiation workers and members of the public to ionising radiations. Supplementary statements to the 1977 recommendations were issued when necessary by the Commission, but developments in the last few years have made it necessary to issue a completely new set of recommendations, officially adopted in November 1990. In publishing these recommendations, the Commission has had three aims in mind: to take account of new biological information and of trends in the setting of safety standards; to improve the presentation of the recommendations; and to maintain as much stability in the recommendations as is consistent with the new information. The recommendations are set out in the form of a main text supported by annexes. The main text contains all the recommendations, together with sufficient explanatory material to make clear the underlying reasoning for policy makers. The supporting annexes contain more detailed scientific information on specific points for specialists.
ICRP Publication 21 contained data for protection against ionizing radiation from external sources. The data were of two kinds, one on the relationships between various radiation quantities, the other on the shielding properties of various materials. Some revised shielding data are now in ICRP Publication 33, which deals with external sources used in medicine: the other kind of data is considered here, but is not intended to apply to the irradiation of patients. The main reason for this revision is to adapt the data and the underlying approach to the Recommendations of the International Commission on Radiological Protection in ICRP Publication 26 and later relevant modifications. It is also necessary to take account of the report on radiation quantities and units from the International Commission on Radiation Units and Measurements and a subsequent report on the determination of dose equivalents. The third reason is to improve the original publication be amending or replacing some data. |
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