![Annals of the ICRP
Published on behalf of the lnternational commission
on Radiological Protection
Editor: H. SMITH, ICRP. Didcot. Ortordshire
International Commis{rn on Rediologkrl hotection l99l3-lgyl
Chairman: hof- R- IL Orrte, National Radio@al Protection Board, Chilton, Didcot, Oxfordshire,
oxn oRQ, u.K.
Vice-Chairman: Mr C. B. Mtiltl4 National Concil on Radiation Protection and Measurements. 79j0 Woodmont
Atsenue, Suite KX), Bethesfu, MD m14, U.S.A.
Scientific Socrctary: Dr. Ir. sdfr, ICRP, P.o. hx No. 35, Didcot, oxfordshire, oxll LRJ, u.K.
Members of ttc Mein Comnisdon of the ICRP
D. Beninson, Buenos Aires
H. J. Dtnster, Oxford
I. A- Ilyin, Moscow
W. Jacobi, Oberschleifheim
H. P. Jammet, Parls
A. Kaul, Salzgitter
D. Li, Taiyuan
J. Li'ne,K, Lodz
H. Matsudaira, Chiba-shi
F. Mettler, Alburyerque
W. K. Sinclair, Bethesda
B. Lindell, Stockholm (Emeritus)
K. Z. Morgan, Atlanta (Emeritus)
L. S. Taylor, Maryland (Emeritus)
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- 2. Annals of the ICRP Published on behalf of the lnternational commission on Radiological Protection Editor: H. SMITH, ICRP. Didcot. Ortordshire International Commis{rn on Rediologkrl hotection l99l3-lgyl Chairman: hof- R- IL Orrte, National Radio@al Protection Board, Chilton, Didcot, Oxfordshire, oxn oRQ, u.K. Vice-Chairman: Mr C. B. Mtiltl4 National Concil on Radiation Protection and Measurements. 79j0 Woodmont Atsenue, Suite KX), Bethesfu, MD m14, U.S.A. Scientific Socrctary: Dr. Ir. sdfr, ICRP, P.o. hx No. 35, Didcot, oxfordshire, oxll LRJ, u.K. Members of ttc Mein Comnisdon of the ICRP D. Beninson, Buenos Aires H. J. Dtnster, Oxford I. A- Ilyin, Moscow W. Jacobi, Oberschleifheim H. P. Jammet, Parls A. Kaul, Salzgitter D. Li, Taiyuan J. Li'ne,K, Lodz H. Matsudaira, Chiba-shi F. Mettler, Alburyerque W. K. Sinclair, Bethesda B. Lindell, Stockholm (Emeritus) K. Z. Morgan, Atlanta (Emeritus) L. S. Taylor, Maryland (Emeritus) t ii, ii fr |.t.. H1 ai H [| fir n,. Hi' ryi- Subscription Information Annals of the /CRP is published as I volume of 4 issues per annum Annual Institutional Subscription Rates 1997: Europe, The CIS and Japan, 393 Dutch Guilders. All other countries US$242. Associated Personal Subscription Rates are available on request lor those whose institutions are library subscribers. Sterling prices exclude VAT. Non-VAT registered customers in the European Community will bL charged the appropriate V{T in addition to the price listed. Prices include postage and insurance and aie subject to change without notice. (Each report will be published as soon as material is ieceived from the ICRp, so ihat issues will not necessarily appear at regular intervals.) Any enquiries relating to subscriptions should b€ sent to: The Americas: Elsevier Scie.nce, Cl:tomer Support Department, PO Box 945, New York, Ny 10010, USA [Tel.: (+l) 212-633-3730(+l) 888 4ES-INFO. Fax: (+ l) 212-633-3680. E-mail: usinfo-f@elsevier.coml. Japan: Elsevier Science Customer Support Department, g-15 Higashi-Azabu l-chome, Minato-ku, Tokyo 106, Japan ltel.: (+3) 5561-5033. Fax: (+3) 5561-5047. E-mail: kyf04035@niftyserv.orjpl. Asia Pacific {exclnding Japan): Elsevier Science (Singapore) Pte Ltd, No. I Temasek Avenue, 17-01 Millenia Tower, Singapore 039192. [Tel.: (+65) 434-3727. Fax: (+65) 337-2230. E-mail: asiainfo@elsevier.com.sg]. Rest of the World: Elsevier Science Customer Service Department, PO Box 211, 1001 AE Amsterdam, The Netherlands. [Tel.: (+31) 20-485-3757. Fax: (+31) 20-495-3432. E-mail: nlinfo-f@elsevier.nl]. Back Issues Back issues of all previously published volumes are available direct from Elsevier Science offices. This journal is indexed/abstracted in: App. Health Phy. Abstr., Biosis Data., CABS and SSSA/CISA/ECA/ISMEC. @-The paper used in this publication meets the minimum requirements ol American National Standard for Information Sciences-Permanence of Paper for Printed Library Materials, ANSI 239.48-19g4. Periodicals postage paid at Rahway, New Jersey. Annats of the ICRP (ISSN 0146-6453) is published four times a year, 11 !|-arch, June, September and December, in one volume, by Elsevier Science Ltd, The boulevard, Langford iane, Kidlington, oxford oX5 lGB, U.K. The annual subscription in the U.S.A. is$242. Annals ofile rinp iidistributed by Mercury Airfreight International Ltd, l0 Camptown Road, Irvington, NJ 07111-1105. POSTMASTER: please snd address corrections to Annals of the ICRP, c/o Elsevier Science RSO, Custoiner Support Department, 655 Avenue of the Americas, New York, NY 10010, USA. B Cc for use agar ADOPTED The Internation
- 4. UK USA JAPAN Elsevier Science Ltd, The Boulevard, Langford Lane, Kidlington, Oxford OX5 lGB, UK Elsevier Science Inc., 660 White Plains Road, Tarrytown, New York 10591-5153, USA Elsevier Science Japan, Tsunashima Building Annex, 3-20-12 Yushima, Bunkyo-ku, Tokyo l13, Japan copyright @ 1997 ICRP and ICRU All rigbts reserved, The International Commission on Rudiological Protection encoursges lhe publication of trtnslations oJ'this report. No part of this publication may he reproduced, stored in a retrieval system or transmitted in any form or by any mesns, electronic, electr ostatic, magnetic tape, mechanical, photocopying, recording or otherwise or repuhlished in any form, without permission in writing from the copyright owner. First edition 1996 rsBN 0 08 042739 I ISSN 0146-6453 Published quarterly (March, June, September, December) SeptemberiDecember 1996 issue Whilst every effort is made by the publishers and editorial board to see that no inaccurate or misleading data, opinion or statement appears in this journal, they wish to make it clear that the data and opinions appearing in the articles and advertisements herein are the sole responsibility of the contributor or advertiser concerned. Acmrdingly, the publishers, the editorial board and editors and their respective employees, oftcers and agents accept no responsibility or liability whatsoever for the consequences of any zuch inaccurate or misleading data, opinion or statement. Drug and dosage selection: The authors have made every efort to ensure the accuracy of the information herein, particularly with regard to drug selection and dose. However, appropriate information souces should be consulted, esp€cially lor new or unfamiliar drugs or procedures. It is the responsibility of every practitioner to evaluate the appropriateness of a particular opinion in the context ofactual clinical situations and with due consideration to new developments. Typeset hy Quorum Technical Services Ltd, Cheltenham Printed and bound in Great Britain by BPC Wheatons Ltd, Exeter fusnord hr&ce fu4' of Terms and Defi IL TNTRODUCTION L QUANTITIES USED E(TERNAL RADIA] al. Introduction 22- The Evolution of Radiation 2.2.1. General 2.2.2. Dose eqr 2.2.3. The max 2.2.4. Conversi, 2.2.5. Dose eqt 2.2.6. Effective 2.2.7. Operatio 2.2.8. ICRP Pu 2.2.9. The Parir 2.2.10. ICRU R 2.2.11. ICRP Pu 2,2.12. ICRU R 2.2.13. Summar; 2-3. Absorbed Dose 2.3.1. Absorbe< 2.3.2. Absorber 2.3.3. Mean ab 2.4. Radiation Weigh 2.4.1. General 2.4.2. Radiatio 2.4.3. Radiatio 2.4.4. Radiatio 2.4.5. Radiatio 2.4.6. Q@)-L 2.4.7. Mean qu 2.4.8. Stopping 2.5. Radiological Pro 2.5.1. General 2.5.2. Organ al 2.5.3. Equivale 2.5.4. Effective
- 6. lv CONTENTS 2.6. Operational Quantities 2.6.1. General 2.6.2. Dose equivalent 2.6.3. Operational quantities for area monitoring 2.6.4. Operational quantities for individual monitoring 3. DETERMINATION OF ABSORBED DOSE DISTRIBUTIONS IN THE HUMAN BODY AND IN ANTHROPOMORPHIC AND OTHER MODELS 3.1. Introduction 3.2. Radiation Field 3.3. Models and Phantoms of the Human Body 3.3.1. Reference man 3.3.2. Simple phantoms 3.3.3. Anthropomorphic models 3.4. Methods of Calculating Absorbed Dose Distributions 3.4.1. Introduction 3.4.2. Transport codes-general features and special codes 3.5. Irradiation Geometries 3.5.1. General 3.5.2. Geometries used with the ICRU Sphere 3.5.3. Geometries used with the ICRU Slab 4. CO}WERSIONCOEFFICIENTS 4.1. Introduction 4.2. General 4.2.1. Radiation energy spectra and mixed radiation fields 4.3. Conversion Coefficients for Photons 4.3.1. Introduction 4.3.2. Special considerations for photons 4.3-3. Methods of calculation 4.3.4. Available data 4.3.5. Conversion coefficients and analysis 4.4. Conversion Coefficients for Neutrons 4.4.1. Introduction 4.4.2. Special considerations for neutrons 4.4.3. Methods of calculation 4.4.4. Available data 4.4.5. Conversion coefficients and analysis: Protection Quantities 4.5. Conversion Coefficients for Electrons 4.5.1. Introduction 4.5.2. Special considerations for electrons 4.5.3. Methods of calculation 4.5.4. Available data 4.5.5. Conversion coefficients and analysis: Protection Quantities 5. RELATIONSHIPS BETWEEN QUANTITIES 5.1. Introduction 5.2. Changes in the Protection and Operational Quantities 5.2.1. General l5 t6 t7 t7 t7 2t 2t 22 24 24 24 24 26 26 27 31 31 33 33 35 35 35 35 36 36 36 37 37 40 50 50 50 5l 53 59 7l 7l 7t 72 72 74 83 83 83 83 I 522. nil{ s23- opq ncU*:dipU fuocdl 5J-l- Gud f32 Arce m 5J3- Indivtutui 53-4- $mmry Cmal Conctusit FTGURES TABLES
- 8. Following the 1977 Recommendations of the International Commission on Radiological Protection (ICRP), the International Commission on Radiation Units and Measurements (ICRU) developed a set of measurable operational quantities to supplement those dosimetric quantities that are specified in the human body by the ICRP, sometimes called protection quantities. The 1990 ICRP Recommendations made some changes to the specification of these protection quantities. As a result, a Joint Task Group of the ICRP and the ICRU was established with the principal aim of determining whether the operational quantities still represent adequately the protection quantities. The conclusion is that, with some exceptions that are not of significance for radiological protection, the operational quantities continue to achieve their objective. The report provides an extensive and authoritative set of data linking field quantities, operational quantities and protection quantities in a way that will be of help to those working in radiological protection. It was agreed that the final report, which has been approved by both Commissions, would be published in the Annals of the ICRP and as an ICRU Report. vi
- 9. This report was prepared by a Joint Task Group of the International Commission on Radiological Protection (ICRP) and the International Commission on Radiation Units and Measurements (ICRU). The terms of reference of the Joint Task Group are discussed in the Introduction (Section 1). The Joint Task Group had the following membership: Full Members R. H. Thomas (Chairman) L. W. Brackenbush G. Dietze J-L. Chartier G. Drexler M. J. Clark H. G. Menzel Corresponding Members R. Griffith B. R. L. Siebert B. Grosswendt M. Zankl N. Petoussi-Henss The membership of ICRP Committee 2 during the period of the Joint Task Group was: A. Kaul (Chairman) F. A. Fry M. Roy A. Bouville J. Inaba J. W. Stather X. Chen I. A. Likhta& D. M. Taylor F. T. Cross H. MCtivier R. H. Thomas G. Dietze H. G. Paretzke K. F. Eckerman A. R. Reddy The ICRU Sponsors of the report were: R. S. Caswell P. M. DeLuca Members of the International Commission on Radiological Protection during the preparation of this report: R. H. Clarke (Chairman) A. Kaul C. B. Meinhold (Vice-Chairman) D. Li D. Beninson J. Liniecki H. J. Dunster H. Matsudaira L. A. Ilyin F. Mettler W. Jacobi W. K. Sinclair H. P. Jammet m H. Smith (Scientific Secretary) Members of the International Commission on Radiation Units and Measurements during the preparation of this report: A. Allisy (Chairman) M. Inokuti A. Wambersie (Vice-Chairman) I. Isherwood R. S. Caswell (Secretary) H. G. Menzel P. M. DeLuca H. G. Paretzke K. Doi H. H. Rossi L. Feinendegen G. F. Whitmore W. R. Ney (Assistant Secretary) vii
- 11. GLOSSARY OF TERMS AND DEFINITIONS OF QUANTITIES Absorbed Dose denoted as D, is the quotient of dE by dm, where dE is the mean energy imparted by ionising radiation to matter of mass dm, thus D,!C dm The unit of absorbed dose is joule per kilogram (J kg-‘ ) and its special name is gray (Gy). Ambient Dose Equivalent denoted as H*(d), at a point in a radiation field is the dose equivalent that would be produced by the corresponding expanded and aligned field in the ICRU sphere at a depth, d, on the radius opposing the direction of the aligned field. The unit of ambient dose equivalent is joule per kilogram (J kg-‘ ) and its special name is sievert (Sv). Directional Dose Equivalent denoted as H’ (d,@, at a point in a radiation field, is the dose equivalent that would be produced by the corresponding expanded field in the ICRU sphere at depth, d, on a radius in a specified direction, fi. The unit of directional dose equivalent is joule per kilogram (J kg- ‘ ) and its special name is sievert (Sv). Dose Equivalent denoted as H, is the product of Q and D at a point in tissue, where D is the absorbed dose and Q is the quality factor at that point, thus H=QD. The unit of dose equivalent is joule per kilogram (J kg-‘ ) and its special name is sievert (Sv). Dose Equivalent Index’ , HI maximum dose equivalent within the ICRU sphere centred at the point in space to which the quantity is assigned. The outer 0.07 mm thick shell is ignored. It was also called the unrestricted dose equivalent index (see ICRU, 1980) (see also ICRU, 1988 for a definition of deep and shallow dose equivalent index). Effective Dose a summation of the equivalent doses in tissues or organs, each multiplied by the appropriate tissue weighting factor. It is given by the expression where HT is the equivalent dose in tissue or organ, T, and wr is the tissue weighting factor ‘ Obsolete quantity; included for completeness. ix
- 12. X GLOSSARY OF TERMS AND DEFINITIONS OF QUANTITIES for tissue, T (see Table 3). The effective dose can also be expressed as the sum of the doubly weighted absorbed dose in all the tissues and organs of the body. Effective Dose Equivalent denoted as HE, is the weighted average of the annual dose equivalents, each weighted by a tissue or organ weighting factor, thus: HE=&& T where HT is the annual dose equivalent in tissue, T, and WT is the tissue weighting factor for tissue, T, as formerly recommended by the ICRP (see Table 1). Energy Imparted denoted as E, by the ionising radiation to matter in a volume is given by: E = Ri” - Rout+ ZQ where Ri, is the radiant energy incident on the volume, i.e. the sum of all the energies (excluding rest energies) of all those charged and uncharged ionising particles that enter the volume; R,,, is the radiant energy emerging from the volume, i.e. the sum of all the energies (excluding rest energies) of all those charged and uncharged ionising particles that leave the volume; and CQ is the sum of all changes of the rest mass energy of nuclei and elementary particles in any interactions that occur in the volume. (In the sum, decreases are denoted by ( + ) and increases are denoted by (-).) The expectation value of E, termed the mean energy imparted and denoted I, is closely related to the definition of the absorbed dose, D. Equivalent Dose denoted as HT,R, is the absorbed dose in an organ or tissue multiplied by the relevant radiation weighting factor (see Table 2), thus: HT,R = WR-DT,R where DT,R is the absorbed dose averaged over the tissue or organ, T, due to radiation R, and wn is the radiation weighting factor for radiation, R. When the radiation field is composed of radiations with different values of wn, the absorbed dose is subdivided into blocks, each multiplied by its own value of wn and summed to determine the total equivalent dose, i.e. HT = &'R.DT,R R The unit of equivalent dose is joule per kilogram (J kg-‘ ) and its special name is sievert (Sv). Fluence denoted as @,is the quotient of dN by da, where dN is the number of particles incident on a sphere of cross-sectional area da, thus:
- 13. GLOSSARY OF TERMS AND DEFINITIONS OF QUANTITIES xi Individual Dose Equivalent, penetrating, H,,(d) the dose equivalent in soft tissue below a specified point on the body at depth, d, which is appropriate for strongly penetrating radiation. Individual Dose Equivalent, superficial, H,(d) the dose equivalent in soft tissue below a specified point on the body at a depth, d, which is appropriate for weakly penetrating radiation (see personal dose equivalent). Kerma, K the quotient of dE,, by dm, where dE,, is the sum of the initial kinetic energies of all the charged ionising particles liberated by uncharged ionising particles in a volume element of mass dm, thus: The unit of kerma is joule per kilogram (J kg-‘ ) and its special name is gray (Gy). Linear Energy Transfer or linear collision stopping power, L, of a material, for a charged particle, is the quotient of dE by df, where dE is the mean energy lost by the particle, owing to collisions with electrons, in traversing a distance dL, thus: Operational Quantity a quantity with which, by means of its measurement, compliance with the system of protection may be demonstrated. Examples of operational quantities are ambient dose equivalent, directional dose equivalent and personal dose equivalent. Organ Dose for radiation protection purposes. It is the mean absorbed dose, DT, in a specified tissue or organ of the human body, T, given by DT = (l/mT) D dm or &T/m= where m-r is the mass of tissue or organ, D is the absorbed dose in the mass element dm, and &Tis the total energy imparted in the tissue or organ. Personal Dose Equivalent denoted as H,,(d), is the dose equivalent in soft tissue at an appropriate depth, d, below a specified point on the body. The unit of personal dose equivalent is joule per kilogram (J kg-‘ ) and its special name is sievert (Sv). Protection Quantities dosimetric quantities specified in the human body by the ICRF’ . Examples of protection quantities are effective dose and equivalent dose.
- 14. Xii GLOSSARY OF TERMS AND DEFINITIONS OF QUANTITIES Quality Factor a function, Q, of unrestricted linear energy transfer, L, in water. Values of Q(L) as a function of L are given in ZCRP Publication 60 (ICRP, 1991a) by the following relations: Q(L) = 1 (L < 10) Q(L) = 0.32L - 2.2 (10 5 L 2 100) Q(L) = 300/,/L (L > 100) where L is expressed in keV pm-‘ . The mean quality factor, Q-r, in a specified tissue or organ, T, is given by QDdm where DT is the mean absorbed dose to the tissue or organ, mr is its mass, and Q and D are the quality factors and the absorbed dose in the mass element dm, respectively. Relative Biological Effectiveness, RBEM the ratio of the absorbed dose of a reference radiation to the absorbed dose of a given test radiation required to produce the same level of response, all other conditions being kept constant. The subscript M refers to a stochastic effect. Radiation Weighting Factor A factor denoted wn, by which the tissue or organ absorbed dose is multiplied to reflect the higher RBEM values for neutrons and alpha particles compared with low LET radiations. Table 2 gives the values of radiation weighting factor used for radiological protection purposes as now recommended by ICRP. When calculation of the radiation weighting factors for neutrons requires a continuous function, the following approximation can be used: where E,, is the neutron energy in MeV. There is no intention to imply any biological meaning to this relationship. It is simply a tool for calculation. For radiation types and energy that are not included in this table, an approximation of wa can be obtained by calculation of Q at a depth of 10 mm in the ICRU sphere: where D(L)dL is the absorbed dose at 10 mm between linear energy transfer, L, and L+dL; and Q(L) is the quality factor at 10 mm [paragraph A14, ZCRP Publication 60 (ICRP, 1991a)l.l ‘ The symbol D(L) has historically been used by the ICRP for the absorbed dose between linear energy transfer, L, and L+ dL. ICRU uses DL for the same quantity. In both instances the more usual mathematical symbol would be dD/dL.
- 15. ... GLOSSARY OF TERMS AND DEFINITIONS OF QUANTITIES Tissue Weighting Factor, wT Xl11 a factor by which the equivalent dose to a tissue or organ is multiplied in order to account for the relative stochastic detriment resulting from the exposure of different tissues and organs. (See Table 3 for the tissue weighting factors as now recommended by ICRP.) Table 1. Tissue weighting factors (ICRP Publicclrion 26)a Tissue or organ Tissue weighting factor, or Gonads 0.25 Bone marrow (red) 0.12 Lung 0.12 Breast 0.15 Thyroid 0.03 Bone surfaces 0.03 Remainder 0.30 “ICRP (1977); see paragraph 105 of ICRP Publication 26 for further details of Remainder Tissues. Table 2. Values for radiation weighting factors (ZCRP Publicution 60)’ Types of energy range of radiation Photons, all energies Electrons and muons, all energiesb Neutrons, energy < 10 keV 16100 keV > 100 keV to 2 MeV > 2-20 MeV > 20 MeV Protons, other than recoil protons, energy > 2 MeV Alpha particles, fission fragments, heavy nuclei Radiation weighting factor, wa 1 1 5 10 20 10 5 5 20 “ICRP (199la). bExcluding Auger electrons emitted from nuclei bound to DNA, for which special microdosimetric considerations are needed. Table 3. Tissue weighting factors” Tissue or organ Tissue weighting factor, wr Gonads 0.20 Bone marrow (red) 0.12 Colon 0.12 Lung 0.12 Stomach 0.12 Bladder 0.05 Breast 0.05 Liver 0.05 Oesophagus 0.05 Thyroid 0.05 Skin 0.01 Bone surface 0.01 Remainder 0.05 *See footnotes on Table 2 of ICRP Puhlicurion 60 for further details.
- 222. I ICRP Publication 54 (Annals of the ICRP Vol. 19 No. l-3) Individual Monitoring for Intakes of Radionuclides by Workers: Design and Interpretation ICRP Publication 53 (Annals of the ICRP Vol. 18 No. l-4) Radiation D ose t o P at ient s .fr om Radiopharmaceutic als ICRP Publication 52 (Annals of the ICRP Vol. 17 No. 4) Protection of the Patient in Nuclear Medicine ICRP Publication 51 (Annals of the ICRP Vol. 17 No. 2/3) Data for (Jse in Protection Against External Radiation ICRP Publication 50 (Annals of the ICRP Vol. 17 No' 1) Lung Cancer Risk from Indoor Exposures to Radon Daughters ICRP Publication 49 (Annals of the ICRP Vol. 16 No. 4) Developmentat Efibcts of lrradiation on the Brain of the Embryo and Fetus ICRP Publication 48 (Annals of the ICRP Vol. 16 No. 2/3) The Metabolism of Plutonium and Related Elements ICRP Publication 47 (Annals of the ICRP Vol. 16 No' l) Radiation Proteclion of Workers in Mines ICRP Publication 46 (Annals of the ICRP Vol. 15 No. 4) Radintion Protection Principles for the Disposal of Solid Radioactive Waste ICRP Publication 45 (Annals of the ICRP Vol. 15 No. 3) Quantitative Bases.for Developing a Unified Index of Harm ICRP Publication 44 (Annals of the ICRP Vol. 15 No. 2) Protection of the Patient in Radiation Therapy ICRP Publication 43 (Annals of the ICRP Vol. 15 No. 1) Principles of Monitoring.for the Radiation Protection of the Population ICRP Publication 42 (Annals of the ICRP Vol. 14 No. 4) A Compilation of the Maior Concepts and Quantities in use by ICRP ICRP Publication 4l (Annals of the ICRP Vol. 14 No. 3) Nonstochaslic Efi'ects of lonizing Radiation ICRP Publication 40 (Annals of the ICRP Vol. 14 No. 2) Protection of the Public in the Event of Maior Radiation Accidents: Princip les .for P lanning ICRP Publication 39 (Annals of the ICRP Vol. 14 No. l) Principles.for Limiting Exposure of the Public to Natural Sources of Radiation ICRP Publication 38 (Annals of the ICRP Vols. I l-13) Radionuclide Transformations: Energy and Intensity of Emissions ICRP Publication 37 (Annals of the ICRP Vol. l0 No. 2/3) Cost-Benefit Analysis in the Optimization of Radiation Protection ICRP Publication 36 (Annals of the ICRP Vol. l0 No. l) Protection against lonizing Radiation in the Teaching of Science ICRP Publication 34 (Annals of the ICRP Vol. 9 No. 2/3) Protection of the Patient in Diagnostic Radiology ICRP Publication 32 (Annals of the ICRP Vol. 6 No. 1) Limits of Inhalation of Radon Daughters by Workers ICRP Publication 30 Limits for Intakes of Radionuclides by Workers Part I (Annals of the ICRP Vol. 2 No. 3/4) Part 2 (Annals of the ICRP Vol. a No. 3/4) Supplement to Part 2 (Annals of the ICRP Vol. 5) Part 3 (Annals of the ICRP Vol. 6 No. 2/3) Supplement A to Part 3 (Annals of the ICRP Vol. 7) B to Part 3 (Annals of the ICRP Vol. 8 No. l-3) Part 4: An Addendum (Annals of the ICRP Vol. 19 No. 4) 0 08 035600 I 0 08 035591 9 0 08 033188 2 0 08 035s87 0 0 08 035579 X 0 08 035203 0 0 08 034827 0 0 08 034020 2 0 08 033666 3 0 08 033665 5 0 08 032336 7 0 08 032335 9 0 08 032334 0 0 08 032333 2 0 08 032302 2 0 08 031503 8 0 08 030761 2 0 08 029817 6 0 08 029818 4 0 08 029797 8 0 08 028864 2 0 08 022638 8 0 08 026832 3 0 08 026833 I 0 08 026834 X 0 08 026835 8 0 08 036886 7 II
- 224. Annals of the ICRP Aims and Scope Founded in 1928, the International Commission on Radiological Protection has, since 1950, been providing general guidance on the widespread use of radiation sources causeci by developments in the field of nuclear energy. The reports and recommendations of the ICRP are available in the form of a review journal, Anncls of the ICRP. Subscribers to the journal will receive each new report as soon as it appears, thus ensuring that they are kept abreast of the latest developments in this important field, and ca,n buiid up a complete set of ICRP reports and recommendations. Single issues of the journal are available separately for those individuals and organizations who do not require a complete set of all ICR.P publications, but would like to have their own copy of a particular report covering their own field of interest. Please order through your bookseller, subscription agent or, in case of difficulty. direct from the publisher. Future publications of the ICRP ICRP Publication -, General Principles for Radiation Protection of Workers (1996197). ICR.P Publication -, Pratection from Potentia! Exposure' Application to Selected Radiation Sources (lee6le1). ICRP Publication -, Age-dependent Doses to Members of the Public from Intake of Radionuclides, Part 6, Entbrya and Fetus (1996197). ICRP Publication -, Indiuidual Monitoring .for Intakes of Radionuclides by Workers: Design and Interpretation" (Update of Publication 54) (199697). ICRP Publication -, Principles for the Pratection of the Public against Chronic Exposure Situations (tee6le7). ICRP Publication -, Genetic Susceptibility to Cancer (1997). ICRP Publication -, Basic Anatomical and Phy.tiological Parameters for use in Radiological Protection, Part 2, Anatomy, Physiology and Elemental Composition (1997 198). ICRP Publication -, Rrsk Estbnation for lulultifactorial Diseases (1997 198). ICRP Publication -, Age-dependent Doses to Members of the Fublicfrom Intake of Radionuclides, Part 7, R"eliability of Dose Cofficients (1997 198). ICRP Publication-, Basic Anatomical and Physiological Parameters.for use in Radiological Protection, Part 3, Respiratory and Digestiue Systems (1997 198). ICRP Publicatton-, Limits.for Inta.kes of Radionuclides b1; Workers: Reuision oJ'Publicatiotr 30(2000). Technical reports Use o.f the Respiratary T'ract Model for Calculating Doses for Specified Inhaled Chemical Forms of Radionuciide (1997). illlllll il ilililil ilililI ilil ilt ilt ililililililltilil il 01 46- 645t C 1996)26 z3 / 4 ;'t - P Printed an,J bound in Great Britain by BPC Wheatons Ltd, Exeter 442