Radiation Protection in Transport of Radioactive Material (IAEA TECDOC-374)

61 Pages·1986·2.988 MB·English

IAEA-TECDOC-374
DISCUSSION OF AND GUIDANCE ON
THE OPTIMIZATION
OF RADIATION PROTECTION
IN THE
TRANSPORT OF RADIOACTIVE MATERIAL
A TECHNICAL DOCUMENT ISSUED BY THE
INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, 1986
DISCD UGNSUASI E IFDOOHOANPT N TNCIOME IZATI FORONA DIATION PROTECTION
IN THE TRANSPORT OF RADIOACTIVE MATERIAL
IAEA, VIENNA, 1986
IAEA-TECDOC-374
Printed by the IAEA in Austria
May 1986
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FOREWORD
The 1e 9e 8S5hR ahetftgeEu dlTriafrttoaoiinfoo snnf psRooar dtioactive
Materials, Safety Seri, e6 .seoN mbodiee sht following requirement:
"201, The radiation exposure of transport workers and the general public
is subject to the requirements specified in the "Basic Safety Standards
r of Radiation Protection: 1982 Edition", Safety Series, 9 .oN IAEA,
Vienna (1982), jointly sponsored by the IAEA, ILO, NBA(OECD), WHO."
Thus, the system of dose limitation set forth in Safety Series No. 9 is
required for the transport of radioactive materials. One component of this
systemf o dose limitatioe ht nsoi ptimizationf o protectior nof sourcesfo
exposure.
e ht nI Forewordo t Safety Series6 .oN (1985 Edition)s aw ti noted that:
"The requirement of the optimization component of the system of dose
limitation establishes that planning, designing, usinr go operatinfgo
sources and practices shall be performed in such a manner that exposures
are as low as reasonably achievable, economic and social factors being
taken into eaBchacsToiucn t .Safety Standards include differential
cost-benefit techniques as a practical form of guidance for performing
optimization of radiation protection. They also suggest that, in any
further reduction in exposures economic and social factors should be
taken into acco ot uesann osts ure hetb f eo asesvtu ailable resourcenis
bringing about that reduction. With regard to protection in the
transport of radioactive materials, consideration must be given to
optimization of (1) requirements related to package design and test
requirements including quan dtenixatt yernal radiation level limitations
a) n2(od perational requireme ehtni rtmofsp lementadtnai o,fon
compliance wi ethAhtg, ency's Regulations."
"The responsibility for the development and optimization of
operational requirements for the implementation and compliance with the
Agency's Regulations rests with Competent Authoritin eiMs ember States
and ewhiinttt hernational organizations concerned. Recognie znhietne gd
r foufrther guid natinhci es e aAhrgetean ,cy po ldtaen vsenliop ,
consultation with Member States, a Safety Series 'Guide for Optimization
of Radiation Protection in the Transport of Radioactive Materials'."
This Technical Document (TECDOC) represents the first step toward
providing the above mentioned Safety Series Guide. Two consultants, Mr. K.
Shaw of the UK and Mr. A. Kasai of Japan, prepared a draft of this TECDOC in
December 1984. Following a review period, the Agency convened a technical
committee (TC-555)n i June 1985o t review comments dna preparew en a draft,
e rseshu slitthif eTne an1gl 9 ar 8ttoee5thwvxe.itre ww tpe hadir cthdu ring
now issued as an Agency Technical Document to aid in the development of
ae pohpplttii cmafitzoiaot nion e pshraitfne c intprilaen ssfpoor t
radioactive materials and to encourage further developments in this field.
Following an appropriate period of application of this technical
documene htAt,g ency plao ntus pdas ttcieo nten dntias ssu ae Safety Series
Go usitude peihpmotprl tementaf tSioao fne. t6yT hSe.eroreiNfeo sre,
comments from interested partiee sra welcomen i dp,na articular commentsno
and further inputo t Appendie rax Vs olicited d,na these shoulde b addressed
to:
The Director (Ref: IAEA-TECDOC-374)
Divisi fooNn uclear Safety
International Atomic Energy Agency
001 xPo.BO .
A-1400 Vienna, Austria
EDITORIAL NOTE
In preparing this material for the press, staff of the International Atomic Energy Agency
have mounted and paginated the original manuscripts and given some attention to presentation.
The views expret osnnse oecdde ssarily reflect the hgoto sfove ernme ehMnt fetosm ber States
or organizations under whose auspices the manuscripts were produced.
The use in this book of particular designations of countries or territories does not imply any
judgement by the publisher, the IAEA, as to the legal status of such countries or territories, of
their authorities and institutions or of the delimitation of their boundaries.
The mention of specific companies or of their products or brand names does not imply any
endorsement or recommendation on the part of the IAEA.
CONTENTS
1. Introduction .................................................... 7
l.l General .................................................... 7
l. 2 Scope ...................................................... 8
2. General principles ..............................................01
1 .2Rof looe ptimizat dindoaen cision making levels ..........01..
2 .A2rf eaoap splication ...................................2.1...
2.2.1 General ............................................21
2.2.2 Population involved ...........................3.1... .
2.2.3 Global appe rhttor aafcnohs port system .........3.1..
2.2.4 Elements of transport .............................. 15
2.3 Methods ...............................................6.1... .
2.3.1 Optimization in the decision making process ........ 16
2.3.1.1 Boundaries for optimization
2.3.1.2 Constraints to optimization
2.3.1.3 Sensitivity analysis
2.3.2 Technir qooupfet simization .....................8.1..
2.3.3 Quantitative techniques ..........................8.1.
2.3.4 The monetary value of the man Sv ................... 19
4 .2Data requirements .......................................0.2..
2.4.1 Radiation protection data .......................... 20
2.4.2 Costs .............................................. 21
2.4.2.1 Costs of radiological protection
2.4.2.2 Cf odosett sriment
2.4.3 Other factors ..................................2.2.. .
3. Applications .................................................... 24
3.1 Basic requirements ......................................... 24
3.2 Analytical assessment ...................................... 26
3.3 The cost and extent of the process ......................... 26
4 .3Radiological protection considerations ....................62.
3.5 Transport environment ..................................7.2...
3.6 Elements of transport ...................................... 28
3.6.1 Design ............................................. 28
3.6.1.1 Specification of the design problem
3.6.1.2 Estimation of protection costs, detriment
and other factors
3.6.1.3 Sensitivity analysis
3.6.1.4 Examples with regard to package design
3.6.2 Maintenance and repair ............................. 32
3.6.3 Prepr atroraatfniso pnort ....................2.3.... .
3.6.4 Package handling ................................... 34
3.6.5 Transport .......................................... 34
3.6.6 Storage-in-trans it ................................. 35
References ........................................................... 37
Appendix I - Glossary of terms .................................. 39
Appendix- II Proceduresr of multi-criteria analysis .............34
Appendix III - Procedures for cost-benefit analysis ............... 45
App- e nVdIi xExposure rdroaaftd aioactive material7 4tr a.n.sp.or t
Appendix V - Examples of optimization in the transport of
radioactive material ............................. 51
f LPoiasr tticipants, Consultants, Comm deCnnotnaotr rsibutors .9..5... .
1. INTRODUCTION
1 .1 General
The 1985 Edition of Safety Series No. 6, the Agency's Regulations for the
Safe Transpof rotR adioactive Material implements (see Forewodnrad
paragraphs 201 and 202) the 1982 Edition of the Basic Safety Standards for
(2)
Radiation Protection. The Basic Safety Standards were jointly produced
by IAEA, ILO, NEA/OECD and WHO and are published as IAEA Safety Series No. 9.
To meet the objectives of radiation protection, the Basic Safety
(3)
Standards use the system of dose limitation recommended by the ICRP
Thi sst hasryehset ecmomponents known bs rJiuaesft liyfication, Optimization
and Individual Dose Limitation. These components have been detailsead
follows(2):
Justification. No practice resulting in human exposure to radiation
should be authorized unless its introduction produces a positive net
benefit, taking into account also the resulting radiation detriment.
s reasonablay wol sa ekept bl exposur els shouldA Optim ization.
achievable, ed csnooncaoimai lc factors being taken into account. This
requirement implies that the detriment from a practice should be reduced
by protective measures to a value such that further reductions become
less important than the additional efforts required.
Individual dose limitatione .hT dose equivalento t individuals fromlla
practices (except for medical and natural radiation exposures) should not
exce eheatdp plicable dose limits. Applying this requirement tim, uesbt
recognized that many present-day practices give rio stde ose equivalents
that will be received in the future. This should be taken into account
to ensure that present or future practices would not be liable to result
i an combined undue expy noiasn udfrioe vidual.
This document providese shgetucio ndnadon eccsh eoytfmspto oef nmeon t
dose limitt aiae t phtsiptraol an ionetss pof rort adioactive material, namely
the optimization of radiation protection. It is recognized that the
techniques r ooupsfte idmizing radiation protee ctcrioaon ntinually developing
and that the guidance provided herein on these techniques can be expected to
evolve with time. Furthermoree ht Agencya sah continuing programmerof
developing doc euhamtpe pnnltoie s chBatat sifioocn Safety Staenhdta rodts
design of radiation protection systems. Since transport of radioactive
materials is crucial to all applications it is important that optimization is
applied and that practical guidance is available in a timely fashion. This
TECa D fOsiiC rst st neipp roviding that guidance.
Generally optimization can be applied to:
routine, normd anaal ccident condition fost ranst pesfo orsart tnih
Safety Sdnea r;6i e.osN
e ehltemf etonrta snsport relao trtiand giation protection which include
design, fabd rminace iapahntrtiete of pnnapoa ranacdc tkeianognia,ng s,
consigning, handling, carriage, storage in transit and receipt of
packages (i.e., the packagings and their radioactive material contents).
Optimi lzsalittiauoant iaoopnptsl iw ehsere radiation exposures afro m
source can be controlled by protective measures and the same requirement can
conceptuae r lublops yflea dnning emergency actiotnuso wthee args e oyuarmc e
of controln I. such situatione hsto ptimization process should take into
account both the consequences and the probability of the event.
A wide range of techniques is available to optimize radiation protection,
includit onnc gtuo,b nfie hntp e,ordt ocedures basen do cost-benefit
analysis. The ICRP has produced a report on cost benefit analysis, published
s iim paatossrI to IIart CCne.RR tcPPo gppn uuibb7zlle3ii cctaa.httaoiitNoo nno tNhoe.r 37
techn yie aaqulbumsse e osd.
2 .S1cope
This document provides guidance for the optimization of radiation
pe rthorttae ncnstf piioroo ran tdioactive materials. Optinmiaz astiio n
important consie dsheetrl aentd ciitdnoiea nosf niroga ndiation protection
systems associated e wphiettrh f notrirma af nndtoscrnp eaoanr stport
operations.s i tI however importanto t remember that case-by-case
optimization of widely used equipment may not be appropriate because it could
nullify the advantages of standardization and could cause a net social
(3 )
loss. Optimization does plaa y parn its etting such standarddnas
specifications and in their subsequent application.
e hTpurposf eo this docume otn pstir ovide discussiod nnaa dveihtc neo
applicatf iooop ntimizatn itior nansport operate ihdoToncsu .ment tdoone s