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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.
The purpose of this report is to consolidate and unify in one
publication, important new information on reference anatomical and
physiological values that has become available sincePublication 23
was published by the ICRP in 1975. There are two aspects of this
work. The first is to revise and extend the information in
Publication 23 as appropriate. The second is to provide additional
information on individual variation among grossly normal
individuals resulting from differences in age, gender, race, or
other factors.
This publication collects, unifies, and expands the updated ICRP
reference values for the purpose of providing a comprehensive and
consistent set of age- and gender-specific reference values for
anatomical and physiological features of the human body pertinent
to radiation dosimetry. The reference values given in this report
are based on: (a) anatomical and physiological information not
published before by the ICRP; (b) recent ICRP publications
containing reference value information; and (c) information in
Publication 23 that is still considered valid and appropriate for
radiation-protection purposes.
Moving from the past emphasis on 'Reference Man', the new report
presents a series of reference values for both male and female
subjects of six different ages: newborn, 1 year, 5 years, 10 years,
15 years, and adult. In selecting referencevalues, the Commission
has used data on Western Europeans and North Americans because
these populations have been well studied with respect to antomy,
body composition, and physiology. When appropriate, comparisons are
made between the chosen reference values and data from several
Asian populations.
The first section of the report provides summary tables of all the
anatomical and physiological parameters given as reference values
in this publication. These results give a comprehensive view of
reference values for an individual as influenced by age and gender.
The second section describes characteristics of dosimetric
importance for the embryo and fetus. Information is provided on the
development of the total body and the timing of appearance and
development of the various organ systems. Reference values are
provided on the mass of the total body and selected organs and
tissues, as well as a number of physiological parameters. The third
section deals with reference values of important anatomical and
physiological characteristics of reference individuals from birth
to adulthood. This section begins with details on the growth and
composition of the total body in males and females. It then
describes and quantifies anatomical and physiological
characteristics of various organ systems and changes in these
characteristics during growth, maturity, and pregnancy. Reference
values are specified for characteristics of dosimetric importance.
The final section gives a brief summary of the elemental
composition of individuals. Focusing on the elements of dosimetric
importance, information is presented on the body content of 13
elements: calcium, carbon, chloride, hydrogen, iodine, iron,
magnesium, nitrogen, oxygen, potassium, sodium, sulphur, and
phosphorus.
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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