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In this report, the Commission provides guidance for the protection
of people living in long-term contaminated areas resulting from
either a nuclear accident or a radiation emergency. The report
considers the effects of such events on the affected population.
This includes the pathways of human exposure, the types of exposed
populations, and the characteristics of exposures. Although the
focus is on radiation protection considerations, the report also
recognises the complexity of post-accident situations, which cannot
be managed without addressing all the affected domains of daily
life, i.e. environmental, health, economic, social, psychological,
cultural, ethical, political, etc. The report explains how the 2007
Recommendations apply to this type of existing exposure situation,
including consideration of the justification and optimisation of
protection strategies, and the introduction and application of a
reference level to drive the optimisation process. The report also
considers practical aspects of the implementation of protection
strategies, both by authorities and the affected population. It
emphasises the effectiveness of directly involving the affected
population and local professionals in the management of the
situation, and the responsibility of authorities at both national
and local levels to create the conditions and provide the means
favouring the involvement and empowerment of the population. The
role of radiation monitoring, health surveillance, and the
management of contaminated foodstuffs and other commodities is
described in this perspective. The Annex summarises past experience
of long term contaminated areas resulting from radiation
emergencies and nuclear accidents, including radiological criteria
followed in carrying out remediation measures.
This report considers the evidence relating to cancer risk
associated with exposure to low doses of low-LET radiation, and
particularly doses below current recommended limits for protection
of radiation workers and the general public. It looks at the
possibility of establishing a universal threshold dose below which
there is no risk of radiation-related cancer. The focus is on
evidence regarding linearity of dose response for all cancers
considered as a group, but not necessarily individually, at low
doses (the so-called linear, no-threshold (LNT) hypothesis). The
report concludes that while existence of a low-dose threshold does
not seem unlikely for radiation-related cancers, it does not favor
the existence of a universal threshold. The LNT hypothesis,
combined with an uncertain dose and dose rate effectiveness factor
(DDREF) for extrapolation from high doses, remains a prudent basis
for radiation protection at low doses and low dose rates.
In the present report, ICRP provides information on radiation doses
to the infant due to intakes of radionuclides in maternal milk. As
in Publication 88 (ICRP, 2001) on doses to the embryo and fetus
following intakes of radionuclides by the mother, intakes by female
members of the public and female workers are addressed. Acute and
chronic intakes are considered at various times before and during
pregnancy as well as during the period of breastfeeding. Dose
coefficients per unit intake by the mother (Sv/Bq) are given for
the selected radionuclides of the same 31 elements for which
age-specific biokinetic models were given in Publications 56, 67,
69, and 71. For these elements, doses were calculated for the most
radiologically significant natural or artificial radionuclides that
might be released into the environment due to various human
activities. Dose coefficients are also given in this report for
radionuclides of an additional four elements: sodium, magnesium,
phosphorus, and potassium.
The first of a series of reports recommending Annual Limits for
Intakes (ALI's) of radionuclides by workers. This report 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. The actual ALI values in
ICRP Publication 30 have become obsolete with the newer dosimetry
and dose limits of ICRP Publication 60, and at present the dose
coefficients in ICRP Publications 68, 69, 71, and 72 should be used
to determine ALI's. However, the vast body of biokinetic
information in Publication 30 still forms the basis of much of the
calculations underlying those later reports.
This part gives metabolic data for 30 further elements, including
Annual Limits on Intakes (ALI's) for their isotopes. The data given
in this report are intended to be used together with the text and
dosimetric models described in ICRP Publication 30, Part 1.
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.
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.
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.
This report 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. Current information
on stem cell characteristics, maintenance and renewal, evolution
with age, location in stem cell "niches", radiosensitivity to acute
and protracted exposures, is presented in a series of substantial
reviews as Annexes concerning haematopoietic tissue, mammary gland,
thyroid, digestive tract, lung, skin and bone. This foundation of
knowledge of stem cells is used in the main text of the report to
provide a biological insight to issues such as the
linear-no-threshold (LNT) model, cancer risk among tissues,
dose-rate effects and changes in the risk of radiation
carcinogenesis by age at exposure and attained age.
This report provides a compendium of current information relating
to radiation dose to patients, including biokinetic models,
biokinetic data, dose coefficients for organ and tissue absorbed
doses, and effective dose for major radiopharmaceuticals based on
ICRP radiation protection guidance. These data were compiled from
ICRP Publications 53, 80, and 106 and related amendments and
corrections. This report also includes new information for
82Rb-chloride, iodide (123I, 124I, 125I, and 131I) and 123I
labelled 2ss-carbomethoxy 3ss-(4-iodophenyl)-N-(3-fluoropropyl)
nortropane (FPCIT). The data presented in this report are intended
for diagnostic nuclear medicine and not for therapeutic
applications.
This publication aims to provide guidance on radiological
protection in the new technology of cone beam computed tomography
(CBCT). CBCT is now used widely by specialists who have little or
no training in radiological protection. This publication provides
recommendations on radiation dose management directed at different
stakeholders, and covers principles of radiological protection,
training, and quality assurance aspects. As with previous ICRP
publications, the Commission hopes that imaging professionals,
medical physicists, and manufacturers will use the guidelines and
recommendations provided in this publication for implementation of
the Commission's principle of optimisation of protection of
patients and medical workers, with the objective of keeping
exposures as low as reasonably achievable, taking into account
economic and societal factors, and consistent with achieving the
necessary medical outcomes.
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 provides the technical basis for SAFs relevant to
internalised radionuclide activity in the organs of the reference
adult male and reference adult female as defined in Publications 89
and 110. SAFs are given for uniform distributions of monoenergetic
photons, electrons, alpha particles, and fission-spectrum neutrons
over a range of relevant energies. Electron SAFs include both their
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. The document further outlines the
computational methodology and nomenclature for assessment 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.
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