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Describes the terms and methods used to assess the radiation exposure of astronauts, and provides data for the assessment of organ doses.
The central dose quantities used in radiological protection are absorbed dose, equivalent dose, and effective dose. The concept of effective dose was developed by the International Commission on Radiological Protection (ICRP) as a risk-adjusted dosimetric quantity for the management of protection against stochastic effects, principally cancer, enabling comparison of estimated doses with dose limits, dose constraints, and reference levels expressed in the same quantity. Its use allows all radiation exposures from external and internal sources to be considered together and summed, relying on the assumptions of a linear non-threshold dose¿response relationship, equivalence of acute and chronic exposures at low doses or low dose rates, and equivalence of external and internal exposures. ICRP Publication 103 provides detailed explanation of the purpose and use of effective dose and equivalent dose to individual organs and tissues. This publication provides further guidance on the scientific basis for the control of radiation risks using dose quantities, and discusses occupational, public, and medical applications. It is recognised that best estimates of risk to individuals will use organ/tissue doses and specific dose risk models. Although doses incurred at low levels of exposure may be measured or assessed with reasonable accuracy, the associated risks are increasingly uncertain at lower doses. Bearing in mind the uncertainties associated with risk projection to low doses or low dose rates, it is concluded that effective dose may be considered as an approximate indicator of possible risk, recognising also that lifetime cancer risks vary with age at exposure, sex, and population group. A further conclusion is that equivalent dose is not required as a protection quantity. It will be more appropriate for limits for the avoidance of tissue reactions for the skin, hands and feet, and lens of the eye to be set in terms of absorbed dose rather than equivalent dose.
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 µm-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.
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 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.
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.
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.
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.
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.
Includes the main text for the whole series of Publication 30, and data on twenty one elements having radioisotopes that are of considerable importance in radiological protection.
Focuses on the reference male and female, including data on mass of the various organs of the body, chemical composition of the body and various tissues and physiological data.
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. This book deals with this topic.
Replaces the previous ICRP Publication 54 on individual monitoring programmes and the interpretation of results of measurements for intakes of radionuclides by workers. This book uses this information and takes account of the new principles for the radiological protection of workers provided in ICRP Publication 75.
Provides the technical basis for SAFs relevant to internalised radionuclide activity in the organs of the reference adult male and reference adult female. This title outlines the computational methodology and nomenclature for assessment of internal dose in a manner consistent with that used for nuclear medicine applications.
Provides a set of data linking the operational quantities defined by ICRU with the dosimetric and protection quantities defined by ICRP. This report presents a basis for designing measurement programmes. It is useful to operational health physicists, medical physicists and those involved in the calibration of instruments and personal dosimetry.
Provides a review of stem cells/progenitor cells and their responses to ionising radiation in relation to issues relevant to stochastic effects of radiation which form a major part of the ICRP system of radiological protection. This volume offers information on stem cell characteristics, maintenance and renewal.
In selecting characteristics of the representative person, three important concepts should be borne in mind: reasonableness, sustainability, and homogeneity. In this report, each concept is explained and examples are provided to illustrate their roles.
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