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. TPRD/B/0340/R8 3 

## Centra l Electricit yGeneratin g Boar d Technolog

yPlanning and Researc

h Divisio n BerkeleyNuclea rLaboratorie s

TH E Q SYSTE M FO R TH E CALCULATIO N O FA . AN D A 2 

### VALUE S WITHI N TH E IAE AREGULATION S FO R TH E SAF E TRANSPORTO FRADIOACTIV E MATERIAL S

B yH.F
. Macdonal d an d E.P
. Goldfinc h

Septembe r1983P. 3

Th e Q Syste mfo r th e Calculatio n o f A . an d AValue s Withi n the IAE ARegulation s fo r th e Saf e Transpor t

o f Radioactiv e Material s

- b y- H.F . Macdonal d and E.P . Goldfinc h

Content s Approve d Classificatio n an d Distributio n Approve d 

# 1A> " Hea d o f Plan t ChemistryBranc h
Date : 

# "tH" Dire c 

# to r \sJ4{^^

Date :

. ; •• ' / - / s • *

T o b e publishe d * Healt han

d Safet yDepartment , CourtenayHouse , Londo nP. 4

V .

1 . INTRODUCTION

I n 197 8 the IAE Aentere d int o a Researc hAgreemen t (No . 2291/CF ) wit h the CEGB entitle d "Releas e Limit s fo r Irradiate d Fue l Transpor t Flasks" . Subsequently , SAGSTRA M(The IAE AStandin g AdvisoryGrou p on the Saf e Transpor t o f Radioactiv e Materials ) strongl yurge d th e Agenc yt o establis h a n internationa l coordinatio n o f research , developmen t and testin g programme s an d t o disseminat e the resulting informatio n t o membe r states . I n Septembe r 197 9 the IAE ACommitte e fo r Contractua l Scientifi c Service s recommende d the initiatio n o f a Coordinate d Researc hProgramm e and the Agenc yapprove d incorporatio n o f the CEGB Researc hAgreemen t int o tha t programme . A n essentia l par t o f the wor k associate d wit hth e CEGB Researc h Agreemen t ha s entaile d a re-examinatio n o f th e dosimetri c model s use d i n th e derivatio n o f th e Typ e Apackag e content s limit s withi n th e IAE A Regulation s fo r the Saf e Transpor t o f Radioactiv e Materials ; thes e limit s ar e als o use d i n specifyin g Typ e B packag e activit yleakag e limits , LS A (lowspecifi c activity ) an d exemptio n limits , etc . Cl , 2] . Th e re-examinatio n o f th e earlie r model s i n tur n resulte d i n th e developmen t o f th e Q system , a n improve d metho d fo r th e evaluatio n o f th e content s limit s fo r specia l form(non-dispersible" i and non-specia l form(dispersible ) materials , th e A an d A „ value s respectively . Th e result s o f thi s wor k hav e bee n reporte d extensivel yelsewher e [3-8 ] an

d hav e bee n considere d b ythe IAE APanel s reviewin g the Transpor t Regulation s an

d b ySAGSTRAM . I n Marc h198 2 the IAE AAdvisor yGroup fo r th e Comprehensiv e Revie wo f th e Regulation s adopte d th e Q syste mfo r the calculatio n o f A . and A „ value s i n th e thir d draf t revisio n o f th e 198 4 Editio n o f th e Transpor t Regulations , subjec t t o revie wi n the ligh t o f comment s receive d frommembe r state s a t a Specia l Workin g Group (SWG ) meetin g convene d i n Londo n i n Septembe r 1982 . Th e revise d method s o f determinin g A . an d A
- value s reporte d her e resul t fromthe discussio n o f th e Q syste ma t the Londo n SWGmeeting , th e participant s a t whic har e liste d i n Appendi xA . Th e earlier , somewha t pragmatic , dosimetri c model s incorporate d i n the 197 3 IAE ATranspor t Regulation s hav e bee n extende d and improve d and no whav e a firme r physica l basi s whic hi s mor e defensibl e i n publi c debate . I n addition , they incorporat e the lates t metaboli c dat a and concept s recommende d i n ICR P Publication s 2 6 an d 3 0 [9-12] . Thi s repor t i s intende d t o provid e a

- lP. 5

comprehensiv e accoun t o f th e basi s o f th e Q syste mand th e detaile d considerations'underlyin g th e method s no wuse d i n th e derivatio n o f A. , and A
- value s withi n th e IAE ATranspor t Regulations . 2 . BACKGROUND Th e variou s limit s fo r th e contro l o f release s o f radioactivit yfrom transpor t package s prescribe d i n th e IAE ATranspor t Regulation s ar e base d upo n th e activit ycontent s limit s fo r Typ e Apackages . Typ e Apackage s ar e intende d t o provid e economica l transpor t fo r larg e number s o f small

activit yconsignments , whil e a t th e sam e time ensurin g a hig hleve l o f safety . Th e content s limit s ar e se t s o a s t o ensur e tha t th e radiologica l consequence s o f sever e damag e t o a Typ e Apackag e ar e no t unacceptabl e an d desig n approva l byth e Competen t Authorit yi s no t required , excep t i n respec t o f criticalit yconsiderations . Activitie s i n exces s o f th e Typ e Apackag e limit s ar e covere d i n th e IAE ARegulation s b yth e requirement s fo r Typ e B packages , whic hd o requir e Competen t Authorit yapproval . Th e desig n requirement s fo r Typ e B package s ar e suc ha s t o reduc e t o a ver ylo wleve l th e probabilit yo f significan t activit yreleas e fro msuc hpackage s a s a resul t o f a ver ysever e accident . Originally , radionuclide s wer e classifie d int o seve n group s fo r transpor t purpose s [13 , 14] , eac hgroup havin g it s Typ e Apackag e content s limit s fo r specia l for mmateria l and fo r materia l i n al l othe r forms . Specia l for mmateria l wa s define d a s tha t whic hwa s non-dispersibl e whe n subjec t t o specifie d tests . I n th e 197 3 Regulation s th e group classificatio n syste mwa s develope d int o th e A.-/A „ syste m[1 , 2] , i n whic heac hnuclid e ha s a Typ e Apackag e content s limit , A

_curies, vhe n transporte d i n specia l for man d a limit , A
- curies , whe n i n non-specia l form . Th e dosimetri c base s o f th e A.-/A 9 syste mrelie d upo n a numbe r o f somewha t pragmati c assumptions . Awhol e bodydos e limi t o f 3 re m(3 0 mSv ) wa s assume d i n the derivatio n o f A , althoug hi n calculatin g A . value s th e exposur e wa s limite d t o 3 Ra t a distanc e o f 3 metre s i n a perio d o f 3 hour s (se e para . 4.1 2 o f referenc e 2) . Also , a n intak e o f 1 0 xA-. , leadin g t o hal f th e maximumpermissibl e annua l intak e fo r a radiatio n worker , wa s assume d i n th e derivatio n o f A- , a s a resul t o f a "median " accident . Th e media n acciden t wa s define d arbitraril ya s on e whic hlead s t o complet e los s o f

- 3 shieldin g and t o a releas e o f 1 0 o f th e packag e content s i n suc ha manne r

- 3 tha t 1 0 o f thi s release d materia l wa s subsequentl ytake n i n bya bystander . Th e Q syste mdescribe d her e include s consideratio n o f a broade r rang e o fP. 6

specifi c exposur e pathway s compare d wit hth e earlie r A./A

- system . Manyo f the assumption s mad e ar e simila r t o thos e stated , o r implied , i n th e 197 3 Regulations , bu t i n situation s involvin g th e intak e o f radioactiv e materia l us e i s mad e o f ne wdat a an d concept s recentl yrecommende d b yth e ICR P [9-12] . I n particular , subjectiv e assumption s ar e mad e regardin g th e exten t o f packag e damag e and releas e o f contents , a s discusse d later , withou t referenc e t o a media n accident . 3 . TH E BASI S O F TH E Q SYSTE M Unde r th e Q syste ma serie s o f exposur e route s ar e considered , eac h o f whic hmigh t lead t o radiatio n exposure , eithe r externa l o r internal , t o person s i n the vicinit yo f a Typ e Apackag e involve d i n a sever e transpor t accident . Th e dosimetri c route s ar e illustrate d schematicall yi n Figur e 1 and lea d t o fiv e content s limi t value s Q. , CL, , Q_ , Q

_and Q_ , fo r externa l A0 L U_ . photo n dose , externa l bet a dose , inhalatio n dose , ski n and ingestio n dos e du e t o contaminatio n transfe r and submersio n dos e respectively . Content s limit s fo r specia l for malph a an d neutro n emitter s and tritiumar e considere d separately . I n addition , consideratio n i s give n t o th e physica l form o f packag e content s wher e physica l limitation s ma yb e mor e restrictiv e tha n radiologica l considerations . Typ e Apackag e content s limit s ar e determine d fo r individua l radio

nuclides , a s i n th e 197 3 Regulations . Th e A . valu e fo r specia l for m material s i s the lesse r o f th e tw o value s Q , and Q_ , whil e th e A „ valu e fo r A H i. non-specia l formmaterial s i s th e leas t o f A . and th e remainin g Q values . Specifi c assumption s concernin g th e exposur e pathway s use d i n th e derivatio n o f individua l Q value s ar e discusse d below , bu t al l ar e base d upo n th e followin g fundamenta l assumptions : a ) Th e effectiv e o r committe d effectiv e dos e equivalen t t o a perso n expose d i n th e vicinit yo f a transpor t packag e followin g a n acciden t shoul d no t excee d the annua l dos e limi t fo r radiatio n workers , namel y 5 0 mS v( 5 rem) . b ) Th e dos e o r committe d dos e equivalen t receive d b y individua l organs , includin g th e skin , o f a perso n involve d i n th e acciden t shoul d no t excee d 0. 5 S v (5 0 rem) , o r i n th e specia l cas e o f th e len s o f th e ey e 0.1 5 S v(1 5 rem) .P. 7

c ) Apeeso n i s unlikel yt o remai n a t 1 metr e fro mth e damage d packag e fo r mor e tha n 3 0 minutes . Her e th e annua l dos e o r intak e limit s fo r radiatio n worker s replac e the earlie r quarterl ylimit s use d i n th e 197 3 Regulations , th e latte r limit s n o longe r bein g include d i n th e recommendation s o f th e ICR P [9] . Thi s approac h wa s considere d b

yth e Londo n SW Gmeetin g a s bein g acceptabl e o n a onc e i n a lifetim e basi s fo r member s o f th e publi c inadvertentl yexpose d nea r the scen e o f a sever e acciden t involvin g a Typ e Apackage . Complianc e wit hth e assumption s (a ) and (b ) abov e i s automaticall yensure d byth e us e o f th e lowes t o f th e stochasti c o r non-stochasti c annua l limi t o n intak e (ALI ) o r th e derive d ai r concentratio n (DAC ) value s recommende d byth e ICR P [10-12] , a s appropriate . Further , th e exposur e perio d o f 3 0 minute s a t a distanc e o f 1 metr e i s a cautiou s judgemen t o f th e incidenta l exposur e o f person s initiall y presen t a t th e scen e o f a n accident , i t bein g assume d tha t subsequen t recover yoperation s tak e plac e unde r healt hphysic s supervisio n and control . Thi s i s considere d t o b e mor e realisti c tha n th e earlie r assumptio n o f exposur e fo r 3 hour s a t a distanc e o f 3 metres . Couple d wit hth e dos e limit s cite d abov e i t lead s t o a limiting.dos e rat e fro mth e damage d packag e fo r whol e bodyphoto n irradiatio n o f 0. 1 Sv. ha t 1 metre . 4 . DOSIMETRI C MODEL S AND ASSUMPTION S I n thi s sectio n th e dosimetri c model s and assumption s underlyin g th e derivatio n o f fiv e principl e Q value s ar e describe d i n detail . Th e specifi c radiatio n pathway s considere d ar e outline d and th e consideration s affectin g th e method s o f derivatio n use d ar e discussed . Q - Externa l Dos e Du e t o Photon s A____

_" ' Th e Q valu e fo r a radionuclid e i s determine d byconsideratio n o f th e externa l radiatio n dos e du e t o gamm a o r x-ray s t o th e whol e bodyo f a perso n expose d nea r t o a damage d Typ e Apackag e followin g a n accident . Th e shieldin g o f th e packag e i s assume d t o b e completel ylos t i n th e acciden t and th e consequen t dos e rat e a t a distanc e o f 1 metr e fro mi t i s limite d t o 0. 1 Sv. h. Assumin g furthe r tha t th e damage d packag e ma yb e treate d effectivel ya s a poin t source , th e fre e ai r exposur e rat e a t 1 metr e ca n b e expresse d a s D = 1. 4 x1 0 xC xE ^ R. h, wher e C i s th e sourc e activit y i n Bq , and E i s th e mea n photo n energyreleas e pe r disintegratio n expresse d ••' n MP V f TS,—L6_l

_Th p ran wnf

var-iar-fn

n i n th e mrniprica l constan t i nP. 8



### I/ .

thi s expressio n fo r photo n energie s i n th e rang e fro m5 0 ke V t o 5 Me V

i s ± 30% , whil e ove r th e sam e energyrang e th e effectiv e dos e equivalen t pe r

'""*" • -2- 1 uni t exposur e i n fre e ai r i s approximatel y0.6 7 x1 0 Sv. R(se e Figur e 1 0 1 2 o f referenc e 17) . Thi s lead s t o a n expressio n fo r Q o f 1.0 7 x1 0 / E Bq , Ay whic hi n derivin g th e result s presente d her e ha s bee n rounde d t o give : 

# ^ A=

# yfevT ' TBq



# '
Th e value s o f E ^ employe d her e wer e evaluate d takin g int o accoun t th e detaile d decayscheme s o f individua l radionuclide s [18] , wit hno.lowe r energylimi t cut
of f applied . Thi s approac hi s no t strictl yvali d fo r E ^ value s belo w5 0 ke V sinc e th e exposur e pe r uni t energyflu xincrease s rapidly , whil e th e effectiv e dos e equivalen t pe r uni t exposur e decreases , wit hdecreasin g gamm a energy . Thes e tw o effect s compensat e t o some degre e s o tha t th e abov e expressio n remain s vali d withi n th e state d limit s down t o abou t 2 0 keV , althoug hfo r vea k gamm a o r sof t x-rayemitter s o f around 1 0 ke V energyi t ma yoverestimat e Q , value s by abou t a n orde r o f magnitude . Thi s effec t i s onl yimportan t wher e E i s dominate d byphoto n emission s i n thi s rang e and ha s bee n ignore d i n th e tabulatio n o f Q value s presente d here . Q „ - Externa l Dos e Du e t o Bet a Emitter s Th e Q

_valu e i s determine d b yconsideratio n o f th e bet a dos e t o th e B ski n o f a perso n expose d followin g a n acciden t involvin g a Typ e Apackag e containin g specia l formmaterial . Th e shieldin g o f th e transpor t packag e i s agai n assume d t o b e completel ylos t i n th e accident , bu t th e concep t o f a residua l shieldin g facto r fo r bet a emitter s (associate d wit hmaterial s suc ha s th e bet a windo wprotector , packag e debris , etc. ) include d i n th e 197 3 Regulation s i s retaine d [2] . Thes e assume d a ver yconservativ e shieldin g facto r o f 3 fo r bet a emitter s o f maximumenergy_ : 2 Me V and withi n th e Q syste mthi s practic e i s extende d t o includ e a rang e o f shieldin g factor s dependen t o n bet a energybase d o n a n absorbe r o f ^ 15 0 mg.c m thicknes s a s follows : E

_(MeV ) 3ma x <Q. 5 0.5-<0. 7 0.7-<1. 0 1.0-<1. 5 1.5-<2. 0 >2. 0 Shieldin g Facto r >10 0 

### 10 0 2 0 

### 6 3 2P. 9

Thes e factor s ar e derive d frc mth e standar d expressio n fo r th e attenuatio n o f beta-ray s a V

a functio n o f energy[19] , and th e approximatio n involve d ca n b e see n fro mFigur e 2 i n whic hth e abov e value s ar e compare d wit hth e continuou s curv e obtaine d from ' th e ful l analytica l expression . I n addition , th e factor s use d her e diffe r fro mthos e originall yuse d i n the Q syste m[4 ] i n tha t followin g th e discussion s a t th e SWGmeetin g n o attemp t i s mad e t o represen t an

yself-shieldin g effect s associate d wit hth e bet a sourc e itself . Base d o n th e dos e limit s cite d earlie r th e bet a dos e equivalen t rat e t o th e ski n a t 1 metr e frc mth e damage d packag e i s limite d t o 1 Sv. h; thi s i s closel yequivalen t t o a n absorbe d bet a dos e rat e i n ai r o f 1 Gy. h Th e variatio n o f bet a dos e rat e wit hmaximumbeta-ra yenerg ya t 1 metr e fro ma 3 7 MB q( 1 mCi ) sourc e i s shown i n Figur e 3 [20];.als o shown a s a soli d lin e i s th e simplifie d representatio n o f thes e dat a whic hi n conjunctio n vit hth e shieldin g factor s and dos e rat e limi t cite d abov e lea d t o th e ful l se t o f Q_

value s a s follows : a E 

### 8ma x (MeV ) 

### <0. 5 0.5-<0. 7 0.7-<1. 0 1.0-<1. 5 1.5-<2. 0 >2. 0 Q B 

### CTBq ) >37 0 2 1 4. 2 0.6 3 0.3 2 0.2 1
Fo r radionuclide s havin g mor e tha n on e beta-ra yend-poin t energy , th e weighte d maximu mbet a energyi s use d i n derivin g Q

_ values , takin g int o accoun t thei r detaile d deca yscheme s [18] . Further , i t shoul d b e note d tha t althoug hth e dos e limi t fo r th e len s o f th e ey e i s lowe r tha n tha t fo r th e ski n (0.1 5 S v c f . 0. 5 Sv) , consideratio n o f th e dept hdose s i n tissu e fo r bet a emitter s

- 2 and i n particula r th e absorptio n a t th e 30 0 mg.c mdept ho f the sensitiv e cell s o f th e len s epitheliumindicate s tha t th e dos e t o th e ski n i s alway s limitin g fo r maximumbet a energie s up t o ^ 4 Me V [9 , 20 , 22] . Specifi c consideratio n o f th e dos e t o th e len s o f th e ey e i s thu s unnecessary . Finally , mentio n shoul d b e mad e o f th e treatmen t o f positro n annihilatio n radiatio n and conversio n electron s i n th e determinatio n o f Q values . Th e latte r ar e treate d a s bet a particle s o f maximumenergyequa l t o th e conversio n electro n energyo r a n equivalen t weighte d valu e wher e mor e tha n on e deca yP.1 0

bee n include d i n th e evaluatio n o f th e bet a dos e t o th e ski n sinc e i t contribute s onl ya n additiona l fe wpercen t t o th e loca l dos e t o th e basa l layer . However , th e 0.5 1 Me V gamma ray s ar e include d i n the photo n energy pe r disintegratio n use d i n the derivatio n o f Q a s discusse d above . Q - Interna l Dos e vi a Inhalatio n \_ i Th e Q r valu e fo r a radionuclid e transporte d i n a non-specia l formi s determine d b

yconsideratio n o f th e inhalatio n dos e t o a perso n expose d t o th e activit yrelease d fro ma damage d Typ e Apackag e followin g a n accident . Complianc e wit hthe limitin g dose s cite d earlie r i s ensure d b yrestrictin g th e intak e o f activit yunde r acciden t condition s t o th e annua l limit s o n intak e (ALI ) recommende d byth e ICR P [10-12] . Th e concep t o f th e "median " acciden t use d i n th e 197 3 Regulation s i s n o longe r employe d sinc e it s definitio n involve d a circula r argument , namel ytha t a media n acciden t wa s on e leadin g

- 3 .. . t o a releas e o f 1 0 o f th e packag e content s couple d wit ha dosimetri c

- 3 mode l vhic hassume d tha t suc ha n acciden t release d 1 0 o f th e packag e

- 3 . content s and tha t 1 0 o f thi s releas e wa s incorporate d int o a person . Unde r th e Q syste ma rang e o f acciden t scenario s is-considered , includin g tha t originall ypropose d fo r th e derivatio n o f Q r , encompassin g accident s occurrin g bot hindoor s and out-of-door s an d includin g th e possibl e effect s o f fires . Thes e ar e discusse d i n detai l i n Appendi xB . Followin g

— 6 discussio n a t the Londo n SW Gmeetin g a n intak e facto r o f 1 0 va s agreed , a s i n th e 197 3 Regulations . However , withi n th e Q syste mthi s valu e

- 3 - 2 represent s a combinatio n o f release s typicall yi n th e rang e up t o 1 0 -1 0 o f th e packag e content s a s a respirabl e aerosol , combine d wit ha n uptak e -4- 3 .. . facto r o f up t o 1 0 -1 0 o f th e release d material . Togethe r vit hth e limitin g dose s cite d earlier , thi s lead s t o a n expressio n fo r th e content s limi t base d o n inhalatio n o f th e form :

AL I (Bq ) _,_

, L IO* 5 Thi s expressio n doe s no t explicitl ytak e accoun t o f th e chemica l formi n vhic hmateria l i s transported , bu t i n applyin g i t us e o f th e mos t restrictiv e o f th e AL I value s recommende d byth e ICR P ensure s tha t th e mos t restrictiv e situatio n i s considered . Wher e th e likel ydegre e o f solubilit y(clas s D , Wo r Y ) o r the chemica l for m(organi c o r inorganic ) o f a particula r radio

nuclid e ar e known , th e degre e o f pessimis mintroduce d bythi s procedur e ca n b e quantifie d b

yreferenc e t o th e tabulate d AL I value s [10-12] .P.1 1

Q - Ski n Contaminatio n an d Ingestio n Dose s Th e Q valu e fo r bet a emitter s i s determine d b yconsideratio n o f th e bet a dos e t o the ski n o f a perso n contaminate d wit hnon-specia l form materia l a s a consequenc e o f handlin g a damage d Typ e Apackage . Thi s i s a dosimetri c rout e whic hwa s no t considere d previously . Th e mode l propose d withi n the Q syste massume s tha t 1 % o f th e packag e content s ar e sprea d 2 . . uniforml yove r an are a o f 1 m ; handlin g o f the debri s i s assume d t o resul t i n contaminatio n o f the hand s t o 10 % o f thi s leve l [21] . I t i s furthe r assume d tha t the expose d perso n i s no t wearin g glove s bu t woul d recognis e the possibilit yo f contaminatio n o r was hthe hand s withi n a perio d o f 5 hours . Take n individuall ythes e assumption s ar e somewha t arbitrary , bu t th e SWGmeetin g conclude d tha t take n a s a whol e theyrepresen t a reasonabl e basi s fo r estimatin g the leve l o f ski n contaminatio n whic hmigh t aris e unde r

- 3 - 2 acciden t conditions . Thi s i s 1 0 x Q m, wit ha dos e rat e limi t fo r th e ski n o f 0. 1 Sv. hbase d o n a 5 hou r exposur e period . Notin g th e equivalenc e o f gray s an

d seivert s fo r bet a irradiation , thes e parameter s couple d wit h th e bet a dos e rat e dat a shown i n Figur e 4 resul t i n th e followin g value s o f Q

_a s a functio n o f weighte d maximumbet a energy . E
. (MeV) Smax <0. 1 0.1-<0.1 5 0.15-<0. 2 0.2-<0. 5 2:0. 5 Q D(TBq ) >4 6 9. 3 2. 3 0.9 3 0.4 6

- 2 Th e dat a o f Figur e 4 ar e th e bet a dos e rat e a t a dept ho f 5-1 0 mg.c mi n

- 2 - 2 tissu e fo r a n extende d plan e sourc e o f 0.3 7 TBq. m( 1 mCi.c m) [22] ; thi s dept hi s tha t recommende d b yth e ICR P fo r the estimatio n o f th e dept ho f the sensitiv e basa l laye r o f the ski n [23] , whil e the soli d line shown i n Figur e 4 i s the simplifie d representatio n o f thes e dat a fo r a representativ e

- 2 basa l laye r dept ho f 7 mg.c m Th e model s use d i n derivin g the Q value s her e mayals o b e employe d t o estimat e the possibl e uptak e o f activit yvi a ingestion . Assumin g tha t a

- 3 2 2 perso n mayinges t al l the contaminatio n from1 0 m(1 0 cm) o f ski n ove r

— 6 a 2 4 hou r perio d [21 ] the resultan t intak e i s 1 0 xQ , compare d wit htha t

- 8P.1 2

vl- .

vi a inhalatio n o f 10 ~ x Q derive d earlier . Notin g tha t th e dos e pe r uni t

intak e vi a inhalatio n i s generall yo f th e sam e orde r o r greate r tha n tha t vi a ingestio n [10-12] , th e inhalatio n pathwa yvil l normall yb e limitin g fo r interna l contaminatio n du e t o bet a emitter s unde r th e Q system . Wher e thi s doe s no t apply , almos t withou t exceptio n Q <<Q_ , and explici t consideratio n o f th e ingestio n pathva yi s unnecessary . 0 - Submersio n Dos e Du e t o Gaseou s Isotope s ^ E Th e Q_ . valu e fo r gaseou s isotope s whic hd o no t becom e incorporate d int o the bodyi s determine d b yconsideratio n o f the submersio n dos e followin g thei r releas e i n an acciden t whe n transporte d a s non-specia l formmaterial s i n eithe r a compresse d o r uncompresse d state . Arapi d 100 % releas e o f th e packag e content s int o a stor e roo mo r carg o handlin g ba yo f dimension s

3 .. . 3x10x1 0 mwit h4 ai r change s pe r hou r i s assumed . Thi s lead s t o a n initia l airborn e concentratio n o f Q /30 0 m, whic hfall s exponentiall ywit ha deca y

- 1 * constan t o f 4 hdu e t o ventilatio n ove r th e subsequen t 3 0 minut e exposur e

- 3 - 3 perio d t o giv e a mea n concentratio n leve l o f 1.44x1 0 xQ

_m. Ove r th e sam e perio d th e concentratio n leadin g t o th e dos e limit s cite d earlie r i s

- 3 4000xDAC Bq. m, vher e DAC i s th e derive d ai r concentratio n recommende d b y th e ICR P fo r 4 0 hour s pe r vee k and 5 0 veek s pe r yea r occupationa l exposur e i n

3 a 50 0 m

roo m[10-12] , hence : Q_ . = 2.8xlO~ 6 xDAC(Bq.m~ 3 ) TBq . Th e us e o f DAC s i n th e derivatio n o f Q her e automaticall yensure s tha t th e mos t restrictiv e limit , i.e . effectiv e dos e equivalent , ski n o r ey e dose , i s applied . Also , th e derivatio n give n her e applie s t o nobl e gase s vhic h ar e no t incorporate d int o th e bodyand vhos e daughte r product s ar e eithe r a stabl e nuclid e o r anothe r nobl e ga s isotope . I n th e fe wcase s vher e thi s conditio n i s no t fulfille d dosimetri c route s othe r tha n submersio n i n a radioactiv e cloud mus t b e considered , a s discusse d belov . 5 . SPECIA L CONSIDERATION S Th e dosimetri c model s describe d i n th e previou s sectio n appl yt o th e vas t majorit yo f radionuclide s o f interes t an d ma yb e use d t o determin e thei r Q value s and associate d A , and A

_values . Hovever , i n a limite d numbe r o f case s the model s ar e inappropriat e o r requir e modification . Th e specia l consideration s vhic happl yi n suc hcircumstance s ar e discusse d furthe r i n thi s section .

- 9 -P.1 3



### Alph a andNeutro nEmitter s Fo r alph a emitter s i t i s no t i ngenera l appropriat e t o calculat e Q . o r A 

### Q value s fo r specia l formmateria l du e t o thei r relativel ywea k gamm a and B bet a emissions . I nth e 197 3 Regulation s a narbitrar yuppe r limi t fo r specia l 3 - formalph a source s o f 1 0 xA
- wa s introduce d[IJ . Ther e i s n o dosimetri c justificatio nfo r thi s procedur e andi nrecognitio no f this , couple dwit h goo drecor di nthe transpor t o f specia l for mmaterial s andth e reductio n i nmanyQ value s fo r alph a emitter s resultin g fro mth e us e o f th e lates t ICR P recommendations , th e Londo nSW Gmeetin g recommende da tenfol dincreas e 3 . . i nthe arbitrar yfacto r o f 1 0 above . Thu s a nadditiona l Q value , 4 Q = 1 0 xQ„ , i s define dfo r specia l formalph a emitter s andliste di n F L th e columnheade dQ . wher e appropriat e i nth e tabulatio no f Q values . A 

### Overal l the specia l for malph a limit s remai nunchange do r ar e increase d slightl ycompare dwit hthos e i nth e 197 3 Regulation s sinc e change s i nICR P dat a reduc e manyo f th e Q value s fo r alph a emitter s byfactor s o f up t o 10 . Finally , i nrespec t o f th e ingestio no f alph a emitter s argument s analogou s t o thos e use dfo r bet a emitter s i nth e discussio no nQ appl yandth e inhalatio nrathe r tha nth e ingestio npathwa yi s alway s mor e restrictive ; henc e th e latte r i s no t explicitl yconsidered . I nth e cas e o f neutro nemitter s i t wa s originall ysuggeste dunde r th e Q syste mtha t ther e wer e n o know nsituation s wit h(ct,n ) o r (y,n ) source s o r 25 2 th e spontaneou s neutro nemitte r C f fo r whic hneutro ndos e woul dcontribut e significantl yt o th e externa l o r interna l radiatio npathway s considere d earlie r [4] , However , i t wa s note da t th e SW Gmeetin g tha t neutro ndos e 25 2 canno t b e neglecte di nth e cas e o f C f sources . Dat a give ni nICR P Publicatio n2 1 fo r neutro nan dgamm a emission s indicate s a dos e rat e o f

3 - 1 25 2 2.5 4 x1 0 rem. ha t 1 metr e fro ma 1 g C f sourc e [24] , Combine dwit h th e dos e rat e limi t o f 1 0 rem. ha t thi s distanc e cite dearlier , thi s lead s

25 2 . . t o a Q valu e ro r C f o f 0.09 5 TBq , whic hi s mor e restrictiv e tha nth e Q valu e o f 1 0 TB qobtaine do nth e basi s o f th e revise dexpressio nfo r specia l formalph a emitters . Th e neutro ncomponen t dominate s th e externa l

25 2 dos e du e t o a C f sourc e andsimila r consideration s appl yt o th e tw o othe r potentia l spontaneou s fissio nsource s C man dCf . Th e Q value s fo r thes e radionuclide s wer e evaluate dassumin g th e sam e dos e rat e conversio n 25 2 facto r pe r uni t activit ya s fo r th e C f sourc e quote dabove , wit hallowanc e fo r thei r respectiv e neutro nemissio nrate s relativ e t o tha t o f thi s source.

- 1 0 -P.1 4

Bremsstrahlun g Radiatio n Th e A./A

_value s tabulate d i n the 197 3 Regulation s ar e subjec t t o a n uppe r cut-of f limi t o f 100 0 C i i n orde r t o protec t agains t possibl e effect s o f Bremsstrahlun g radiatio n [2j . Withi n the Q syste mthi s cut-of f i s retaine d a t 4 0 TBq . However , followin g discussio n a t the SWGmeetin g i t i s no wrecognise d a s an arbitrarycut-of f and i s no t specificall yassociate d wit hBremsstrahlun g radiatio n o r an yothe r dosimetri c consideration . Paren t Nuclide s o f Short-Live d Daughter s Th e specia l cas e o f short-live d daughter s whic hmaycome int o equi

libriu mwit ha longe r live d paren t durin g transi t i s treate d unde r th e Q system a s i n the 197 3 Regulation s [2] . Thus , base d o n a n assume d maximum journe ytime o f 5 0 day s short-live d daughter s o f half-lif e les s tha n 1 0 day s ar e assume d t o b e i n equilibriumwit ha longe r live d parent . I n suc hcase s Q values , and henc e A./A „ values , fo r bot hth e paren t and daughte r nuclide s ar e calculate d and th e mos t limiting value s ar e assigne d t o th e parent . I t wa s furthe r agree d a t the Londo n SWGmeetin g tha t wher e thi s procedur e ha d bee n applie d thi s woul d b e indicate d i n al l futur e tabulation s o f A an d A „ values . Finally , i n case s wher e daughte r nuclide s hav e half-live s eithe r greate r tha n 1 0 day s o r than tha t o f th e parent , th e paren t and suc h daughter s shoul d b e treate d a s mixture s o f differen t radionuclide s an d thei r Typ e Apackag e content s limit s determine d a s discusse d below . Th e tabulatio n o f A./A

_value s considere d belo wha s bee n expande d beyond tha t give n i n th e 197 3 Regulation s t o includ e al l radioisotope s of-half-lif e _ : 1 0 days . Tritiuman

d it s Compound s I n the cas e o f bot hinorgani c and organi c form s o f tritiu mth e dosimetri c model s discusse d earlie r resul t i n Q value s i n exces s o f th e arbitrary 4 0 TB qcut-of f limi t fo r A_/A

_value s adopte d i n th e Q system . However , du e t o the specia l biologica l behaviou r o f tritiu mand ' it s compound s additiona l concentratio n limit s ar e necessaryfo r thi s radionuclide . A rang e o f possibl e acciden t scenario s involvin g the releas e o f tritiu mwit h consequen t wettin g o f the ski n o f the hand s o f expose d persons , an d inhalatio n o f saturate d vapou r i n a confine d spac e o r out-of-door s ar e considere d i n Appendi xC ; thes e lead t o concentratio n limit s o f 5 0 Ci. 1 , 5 C i 1 and 2 0 C i 1 respectively . Followin g discussio n a t th e SWG

.... . - 3 meetin g a concentratio n limi t fo r tritiu mand it s compound s o f 1 PBq. m (2 7 Ci. l ) wa s determine d a s bein g appropriat e t o cove r suc hcases , t o b e applie d i n additio n t o the A./A , valu e limit s o f 4 0 TBq .

- 1 1 -P.1 5

Lo wSpecific'Activit yMaterial s Th e 1 9 7 3 IAE ATranspor t Regulation s recognise d a categoryo f material s whos e specifi c activitie s ar e s o lowtha t i t i s inconceivabl e tha t a n intak e coul d giv e ris e t o a significan t radiatio n hazard , namel ylo wspecifi c activit y(LSA ) materials . Thes e wer e define d i n term s o f a mode l whic h assume s tha t i t i s mos t unlikel ytha t a perso n woul d remai n i n a dust y atmospher e long enoug ht o inhal e mor e tha n 1 0 mg o f materia l [2] . Thi s mode l i s retaine d withi n the Q syste man d lead s t o an LS Alimi t o f

- 4 - 1 1 0 xQ g ; thu s the Q value s fo r thos e radionuclide s whos e specifi c activit yi s belo wthi s leve l ar e liste d a s "Unlimited" . I n the case s wher e thi s criterio n i s satisfie d the radioactivit yassociate d wit h1 0 m g o f the nuclid e i s les s tha n the appropriat e AL I valu e recommende d b yth e ICRP . Natura l uraniu

mand thorium , deplete d uraniuman d othe r material s suc h 23 8 23 2 23 5 a s U , Th , U , etc . satisf yth e abov e LS Acriterion , a s doe s uranium 23 5 23 5 enriche d t o < 5 % i n U . However , fo r Uenrichment s i n th e rang e from 5 t o 20 % the permitte d intake s o f materia l estimate d o n th e basi s o f th e mode l outline d abov e rang e fro m1 0 t o 2. 7 mg . Thes e level s o f intak e compar e wit ha maximumpermitte d dail yintak e o f 2. 5 mg o f uraniumrecommende d b y th e ICR P o n the basi s o f chemica l toxicit yconsideration s [25] . Suc h consideration s wil l b e mor e restrictiv e tha n the radiologica l limit s 23 5 embodie d withi n the Q syste mfo r Uenrichment s u p t o ^ 20% , althoug h following the practic e i n the 197 3 Regulation s theyar e no t take n int o accoun t i n tabulatin g th e Q value s and associate d A./ Avalue s fo r uranium isotopes . Afurthe r consideratio n relevan t t o LS Amaterial s i n th e contex t o f the ski n contaminatio n mode l use d i n the derivatio n o f Q i s th e mas s o f materia l whic hmigh t b e retaine d o n the ski n fo r an ysignifican t perio d o f time . Th e consensu s vie wo f th e Londo n SWGmeetin g wa s tha t typicall y

- 2 1-1 0 mg.c m

o f dir t presen t o n the hand s woul d b e readil ydiscernabl e an d woul d b e remove d promptl yb ywipin g o r washing , irrespectiv e o f th e possibl e presenc e o f radioactivity . I t wa s agree d tha t the uppe r extrem e o f thi s rang e wa s appropriat e a s a cut-of f fo r the mas s o f materia l retaine d o n the ski n an

d i n combinatio n wit hthe ski n contaminatio n mode l fo r Q discusse d -5- 1 earlier , thi s result s i n an LS Alimi t o f 1 0 xQ g . O n thi s basi s Q value s fo r radionuclide s fo r whic hthi s criterio n applie s ar e als o liste d a s "Unlimited " i n th e tabulatio n o f Q values .P.1 6

Rado n and it £ Daughte r Product s A s note d earlier , the derivatio n o f Q applie s t o nobl e gase s whic h

_ . ar e no t incorporate d int o the bod yand whos e daughte r product s ar e eithe r a stabl e nuclid e o r anothe r nobl e gas . I n a fewcase s thi s conditio n i s no t fulfille d an

d dosimetri c route s othe r tha n externa l exposur e du e t o submersio n i n a radioactiv e cloud mus t b e considere d [26] . Th e onl ycas e o f practica l importanc e withi n the contex t o f the IAE ARegulation s i s tha t 22 9 o f Rn wher e the lun g dos e associate d wit hth e inhalatio n o f the short

live d rado n daughte r product s ha s receive d specia l consideratio n b ythe ICR P [27] . 22 2 I n derivin g the Q value s fo r R n her e ful l accoun t i s take n o f the daughte r radiations , rathe r than applyin g the mos t restrictiv e o f the shorte r live d daughte r produc t Q value s a s discusse d earlier . Th e inclusio n o f the daughter s i n thi s manne r result s i n a smal l reductio n i n th e Q and 22 2 . Q value s compare d wit hthos e obtaine d o n the basi s o f th e R n radiation s o alone . Th e correspondin g Q valu e i s 3. 6 TBq ; however , allowin g fo r a 100 % -3- 2 releas e o f radon , rathe r tha n th e 1 0 - 1 0 aeroso l releas e fractio n incorporate d i n the Q model , thi s reduce s t o a Q valu e i n th e rang e

- 3 - 2 Z2 2 3. 6 x1 0 t o 3. 6 x1 0 TBq . Further , treating R n plu s it s daughter s

- 3 a s a nobl e ga s result s i n a Q valu e o f 4. 2 x1 0 TBq , toward s th e lowe r F end o f the rang e o f Q

_values , and thi s i s the Typ e Apackag e non-specia l 22 2 formlimi t cite d fo r R n i n the tabulatio n o f Q values . 6 . TABULATIONO F Q VALUE S Aful l listing o f Q value s determine d o n the basi s o f the model s describe d i n th e previou s section s i s give n i n Tabl e 1 . Als o include d ar e the correspondin g Typ e Apackag e A . an d A
- content s limi t value s fo r specia l formand non-specia l formmaterial s respectively . Th e Q value s show n i n Tabl e 1 hav e bee n rounde d t o 2 significan t figure s and the A . and A

_value s t o on e significan t figure ; i n the latte r cas e th e arbitrary4 0 TB qcut-of f ha s als o bee n applied . Acompariso n o f A./ Avalue s determine d o n the basi s o f th e Q syste m wit hthos e i n the 197 3 Regulation s i s presente d i n Figur e 5 fo r a repre sentativ e rang e o f radionuclides . I n general , th e Q syste mvalue s li e withi n a facto r o f 2- 3 o f the earlie r values . Wher e majo r variation s occu r thes e ar e generall yassociate d wit hreduction s i n th e Typ e Apackag e content s limit s fo r bet a emitter s determine d b yQ

_an d particularl yQ_ . a u



### - 1 3P.1 7

I n addition, " relaxation s i n the content s limit s occu r fo r some specia l for m alph a emitter s du e t o the revise d definitio n o f Q an d i n certai n instance s du e t o change s i n dosimetri c dat a recommende d b ythe ICRP , a s i n the cas e f 90 c o t Sr . I n drafting the 197 3 Regulation s the IAE Aconsidere d the retentio n o f a grou p classificatio n system , rathe r tha n listing individua l A , an d A, , value s fo r eac hradionuclid e (se e para . 4.0 6 o f referenc e 2) . Inspectio n o f the A, an

d A ? value s give n i n Tabl e 1 indicate s tha t a groupin g o n the basi s o f thre e group s pe r decade , sa yi n th e rati o 1:2:5 , woul d no t involv e undu e los s o f accurac yi n rounding . However , the Londo n SWGmeetin g fel t .o n balanc e tha t the individua l listing use d i n the 197 3 Regulation s ha d no t prove d inconvenien t an d shoul d b e retaine d fo r th e present . Consideratio n o f Physica l Propertie s Afurthe r facto r considere d b yth e SW Gmeetin g wa s the nee d t o appl y additiona l limit s fo r material s whos e physica l propertie s migh t rende r invali d th e assumption s use d i n derivin g th e Q value s discusse d above . Suc hconsideration s ar e relevan t t o material s whic hma ybecom e volatil e a t the elevate d temperature s whic hcoul d occu r i n a fire , o r whic hmayb e transporte d a s veryfinel ydivide d powders , and especiall yfo r th e mode l use d t o evaluat e th e Q values . However , o n balanc e i t wa s fel t tha t onl y

- 6 i n the mos t extrem e circumstance s woul d th e assume d intak e facto r o f 1 0 b e exceede d an

d tha t specia l modificatio n o f th e Q „ mode l wa s unnecessar y fo r thes e materials . Multipl e Exposur e Pathway s Followin g th e 197 3 Regulation s th e applicatio n o f th e Q syste ma s describe d her e treat s the derivatio n o f eac hQ value , and henc e eac h potentia l exposur e pathway , separately . I n general , thi s wil l resul t i n complianc e wit hthe dosimetri c criteri a define d earlie r provide d tha t the dose s incurre d b

yperson s expose d nea r a damage d packag e ar e dominate d b y on e pathway . However , i f two o r mor e Q value s closel yapproac heac hothe r thi s wil l no t necessaril yb e the case . Fo r example , i n the cas e o f a radionuclid e transporte d a s a specia l formmateria l fo r whic hQ = Q , the effectiv e dos e equivalen t and ski n dos e t o an expose d perso n coul d bot h approac h5 0 mS vand 0. 5 S vrespectivel yo n th e basi s o f th e Q syste mmodels . Examinatio n o f Tabl e 1 show s tha t thi s consideratio n applie s onl yt o a relativel ysmal l numbe r o f radionuclide s and fo r thi s reaso n th e independen t treatmen t o f exposur e pathway s i s retaine d withi n th e Q system .P.1 8

SUMMARY Thi s repor t contain s a comprehensiv e descriptio n o f the Q system , a n improve d metho d fo r evaluatin g th e Typ e Apackag e content s limi t Aan d A . value s withi n the IAE ARegulation s fo r the Saf e Transpor t o f Radioactiv e Materials . Th e wor k reporte d her e wa s performe d i n collaboratio n wit hthe Board' s Healt han

d Safet yDepartmen t unde r the term s o f Researc hAgreemen t No . 2291/CF , whic hform s par t o f the IAE ACoordinate d Researc hProgramm e o n the Saf e Transpor t o f Radioactiv e Materials . Th e Q syste mwa s adopte d b ythe IAE Ai n Marc h198 2 fo r the calculatio n o f A. , an d A

_value s t o b e publishe d i n the 198 4 revise d editio n o f th e Transpor t Regulations . Thi s presen t repor t wa s prepare d a t the reques t o f the Agenc yfo r publicatio n a t the same time a s the revise d regulation s late r nex t year . Fo r thi s reaso n the forma t use d i s somewha t differen t fro mtha t o f standar d TPR D reports , following instea d tha t use d b ythe Agenc yi n it s publications .P.1 9

CONTENT S 1 . INTRODUCTION 2 . BACKGROUND 3 . TH E BASI S O F TH E Q SYSTE M 4 . DOSIMETRI C MODEL S AN D ASSUMPTION S Q - Externa l Dos e Du e t o Photon s ^ A Q - Externa l Dos e Du e t o Bet a Emitter s Q - Interna l Dos e vi a Inhalatio n L i Q - Ski n Contaminatio n an d Ingestio n Dose s Q - Submersio n Dos e Du e t o Gaseou s Isotope s E 5 . SPECIAL CONSIDERATION S Alph a an

d Neutro n Emitter s Bremsstrahlun g Radiatio n Paren t Nuclide s o f Short-Live d Daughter s Tritiumand it s Compound s Lo wSpecifi c Activit yMaterial s Rado n an

d it s Daughte r Product s 6 . TABULATIONO F Q VALUE S Consideratio n o f Physica l Propertie s Multipl e Exposur e Pathway s Mixture s o f Radionuclide s 7 . CONCLUSION S REFERENCE S APPENDI XA- Participant s i n th e IAE ASpecia l Workin g Group Meetin g hel d

i n London , 3 1 Augus t - 2 Septembe r 198 2 APPENDI XB - Intak e Factor s fo r Typ e APackag e Transpor t Accident s APPENDI XC - Concentratio n Limit s fo r Consignment s o f TritiumTransporte d

i n Typ e APackage sP.2 0

Mixtures_o f Radionuclide s Finally , i t i s necessar yt o conside r th e packag e content s limit s fo r mixture s o f radionuclides , including the specia l cas e o f mixe d fissio n products . Fo r mixture s whos e identitie s an d activitie s ar e known i t i s necessaryt o sho wthat :
I B(i)/ A(i ) H

1 o r I 3(i)/A 2 (i ) S 1 , i i wher e B(i ) i s the activit yo f radionuclid e i i n th e mixture , an d A_(i ) an

d A_(i ) ar e the Aan d Avalue s fo r tha t radionuclide . I n the cas e o f mixe d fissio n product s th e compositio n o f th e mixtur e wil l i n genera l b e dependen t upo n th e irradiatio n histor yand coolin g perio d o f the fissil e materia l involved . I n addition , the fissio n product s wil l normall yb e accom panie d b

yalph a emitting transurani c isotopes . I n principl e th e inequalitie s give n abov e mayb e applie d i n suc hcase s bu t wher e th e detaile d compositio n o f th e mixtur e i s unknown the lowes t possibl e A . an d A
- value s mayb e used .

- 5 O n thi s basi s A . =0. 1 TB qan d A- . = 2x1 0 TB qfo r unknown mixtures , o r i f th e presenc e o f alph a emitter s ca n b e discounte d A . = 0-. 2 TB qand A
- = 0.0 2 TBq . • 7 . CONCLUSIONS v Th e Q syste mdescribe d her e represent s a developmen t and extensio n o f th e A./A- , syste muse d i n th e 197 3 IAE ATranspor t Regulation s fo r th e deter

minatio n o f Typ e Apackag e content s an d othe r limits . I t incorporate s th e lates t recommendation s o f th e ICR P and byexplicitl yidentifying th e dosi

metri c consideration s underlyin g th e derivatio n o f thes e limit s provide s a firme r and mor e defensibl e basi s fo r th e Regulations . Overall , th e adoptio n o f th e Q syste mintroduce s onl yrelativel ymino r variation s i n th e A . and A _ value s compare d wit hthos e i n th e 197 3 Regulations . Wher e majo r variation s occur , sa

yb ygreate r tha n a facto r o f 2-3 , thes e ar e generall yassociate d wit hreduction s i n th e Typ e Apackag e content s limit s fo r bet a emitter s determine d b

yQ

_an d particularl yQ_ . Thi s latte r Q valu e refer s t o a dosimetri c rout e no t previousl yconsidere d i n th e Regulations , namel ybet a contaminatio n o f the ski n o f expose d persons . Isolate d relaxation s i n th e content s limit s occu r du e t o change s i n dosimetri c dat a introduce d i n ICR P 9 0 Publicatio n 30 , a s i n th e cas e o f Sr , and mor e generall yi n the cas e o f specia l for

malph a emitter s du e t o th e revise d definitio n o f 0_ . Finally , the Q syste mca n als o b e applie d t o th e specificatio n o f permitte d leakag eP.2 1

limit s fo r Typ e 3 packages , exemptio n and LS A(lo wspecifi c activity ) limits , etc. , i n a simila r manne r t o th e us e o f A_/A

_value s i n th e 197 3 IAE ATranspor t Regulations . ACKNOWLEDGEMENT S Th e author s wis ht o expres s thei r appreciatio n t o th e member s o f th e Londo n SW Gmeetin g fo r thei r contribution s t o th e refinemen t o f th e origina l Q syste mconcepts . I n particula r t o Dr . Keit hEckerma n o f th e Healt hand Safet yDivision , ORNL , wh o undertoo k th e verificatio n o f th e Q value s unde r th e sponsorshi p o f th e U S Departmen t o f Transportation , and t o Mr . Ke n Sha w o f th e NRP B wh o provide d AL I value s fo r radionuclide s no t include d i n ICR P Publicatio n 30 . Finally , i t i s a pleasur e t o acknowledg e th e continuin g interes t an d encouragemen t receive d fro mMr . Geral d Swindell , formall yo f th e IAE ADivisio n o f Nuclea r Safet yan d Environmenta l Protection , durin g th e developmen t o f th e Q system . REFERENCE S 1 . IAEA , Regulation s fo r th e Saf e Transpor t o f Radioactiv e Materials , 197 3 Revise d Editio n (a s Amended) , Safet ySerie s No . 6 , IAEA , Vienna , 1979 . 2 . IAEA , Advisor yMateria l fo r th e Applicatio n o f th e IAE ATranspor t Regulations , 2nd Ed. , Safet ySerie s No . 37 , IAEA , Vienna , 1982 . 3 . H.F . Macdonal d and E.P . Goldfinch , "A n Alternativ e Approac ht o th e A./A

- Syste mfo r Determinin g Packag e Content s Limit s and Permitte d Release s o f Radioactivit yfro mTranspor t Packages" , p p 48-5 6 i n Proceeding s o f th e Sixt hInternationa l Symposiumo n Packagin g an d Transportatio n o f Radioactiv e Materials , Berli n (West) , Nov . 10-14 , 1980 . 4 . H.F . Macdonal d and E.P . Goldfinch , Radiat . Prot . Dosim. , 1:2 9 (1981) . 5 . H.F . Macdonal d and E.P . Goldfinch , Radiat . Prot . Dosim. , 1:19 9 (1982) . 6 . E.P . Goldfinc hand H.F . Macdonald , Radiat . Prot . Dosim. , 2:7 5 (1982) . 7 . E.P . Goldfinc hand H.F . Macdonald , " ARevie wo f som e Radiologica l Aspect s o f th e IAE ARegulation s fo r th e Saf e Transpor t o f Radioactiv e Materials" , pp 205-1 1 i n Proceeding s o f th e Thir d Internationa l Symposiumo f th e SRP , Radiologica l Protectio n - Advance s i n Theor yand Practice , Inverness , Scotland , Jun e 6-11 , 1982 .8 . E.P
- Goldfinc han d H.F . Macdonald , "IAE ARegulation s fo r the Saf e Transpor t o f Radioactiv e Materials : Revise d A . and A
- Values" , pp i n Proceeding s o f th e Sevent hInternationa l Symposiumo n Packagin g and Transportatio n o f Radioactiv e Materials , Ne wOrleans , La. , May15-20 , 1983 . 9 . ICRP , Publicatio n 26 , Recommendation s o f th e Internationa l Commissio n o n Radiologica l Protection , Pergamo n Press , Oxford , 1977 . 10 . ICRP , Publicatio n 30 , Par t 1 , Limit s fo r Intake s o f Radionuclide s b y Workers , Pergamo n Press , Oxford , 1980 . 11 . ICRP , Publicatio n 30 , Par t 2 , Limit s fo r Intake s o f Radionuclide s by Workers , Pergamo n Press , Oxford , 1981 . 12 . ICRP , Publicatio n 30 , Par t 3 , Limit s fo r Intake s o f Radionuclide s by Workers , Pergamo n Press , Oxford , 1982 . 13 . IAEA , Regulation s fo r th e Saf e Transpor t o f Radioactiv e Materials , Safet ySerie s No . 6 , IAEA , Vienna , 1961 . 14 . IAEA , Regulation s fo r th e Saf e Transpor t o f Radioactiv e Materials ,

196 7 Edition , Safet ySerie s No . 6 , IAEA , Vienna , 1967 . 15 . R.G . Jaege r (Ed.) , Engineerin g Compendiumo n Radiatio n Shielding , Vol . I Shieldin g Fundamental s and Methods , Springer-Verlag , Berlin-Heidelberg , 1968 . 16 . G.W.C . Kay e and T.H . Laby , Table s o f Physica l and Chemica l Constant s an d Som e Mathematica l Functions , 12t hEd. , Longmans , London , 1959 . 17 . R . Krame r and G . Drexler , Radiat . Prot . Dosim. , 3:1 3 (.1982) . 18 . CM . Ledere r an d V.S . Shirle y(Eds.) , Tabl e o f Isotopes , 7t hEd. , Joh n Wile yan d Son s Inc. , Ne wYork , 1979 . Se e als o ICRP , Publicatio n 3S , Tas k Croup o n Dos e Calculation s - Energyand Intensit yDat a fo r Emission s Accompanyin g Radionuclid e Transformations , t o b e published , 1984 . 19 . J.J . Fitzgerald , G.L . 3rownel l and F.J . Mahoney , Mathematica l Theor y o f Radiatio n Dosimetry , Gordo n and Breac hScienc e Publisher s Inc. , Ne vYork , 1967 . 20 . W.G . Cross , Table s o f Bet a Dos e Distributions , AEC L Repor t 2793 , 1967 . 21 . H.J . Dunster , MaximumPermissibl e Level s o f Ski n Contamination , UKAE ARepor t AHS3(RP)R78 , 1967 .P.2 3

--22 . M.R . Bailey , BETA : ACompute r Progra mfo r Calculatin g 3eta-dos e Rate s

fromPoin t and Plan e Sources , CEG B Repor t RD/B/N2763 , 1973 . 23 . ICRP , Publicatio n 23 , Tas k Group Repor t o n Referenc e Man , Pergamo n

Press , Oxford , 1975 . 24 . ICRP , Publicatio n 21 , Dat a fo r Protectio n agains t Ionisin g Radiatio n

fro mExterna l Sources : Supplemen t t o ICR P Publicatio n 15 , Pergamo n Press , Oxford , 1973 . 25 . ICRP , Publicatio n 6 , Recommendation s o f th e Internationa l Commissio n

o n Radiologica l Protectio n (a s Amende d ,195 9 an d Revise d 1962 ) , Pergamo n Press , Oxford , 1964 . 26 . A . Fairbairn , F . Morle yand W . Kolb , "Th e Classificatio n o f Radio

nuclide s fo r Transpor t Purposes" , pp 44-6 6 i n Th e Saf e Transpor t o f Radioactiv e Material s (R . Gibso n Ed.) , Pergamo n Press , Oxford , 1966 . 27 . ICRP , Publicatio n 32 , Limit s fo r Inhalatio n o f Rado n Daughter s by Workers , Pergamo n Press , Oxford , 1981 . 28 . D.H . Lohmahn, "Transpor t o f Radioactiv e Materials : ARevie wo f Damag e

t o Package s fro mth e Radiochemica l Centr e durin g Transport" , pp 818-2 5 i n Proceeding s o f th e Sixt hInternationa l Symposiumo n Packagin g and Transportatio n o f Radioactiv e Materials , Berli n (West) , Nov . 10-14 , 1980 . 29 . A . Hadjiantonion , J . Armirioti s and A . Zannos , "Th e Performanc e o f

Typ e APackagin g unde r Ai r Cras hand Fir e Acciden t Conditions" , pp 826-3 2 i n Proceeding s o f th e Sixt hInternationa l Symposiumo n Packagin g and Transportatio n o f Radioactiv e Materials , Berli n (West) , Nov . 10-14 , 1980 . 30 . C.3.G . Taylor , "Radioisotop e Package s i n Crus hand Fire" , pp 1347-5 4

i n Proceeding s o f th e Sixt hInternationa l Symposiumo n Packagin g an d Transportatio n o f Radioactiv e Materials , Berli n (West) , Nov . 10-14 , 1980 . 31 . K . Stewart , "Principa l Characteristic s o f Radioactiv e Contaminant s whic hma yAppea r i n th e Atmosphere" , p p 321-6 0 i n Progres s i n Nuclea r Energy , Serie s XI I Healt hPhysics , Volum e II , Pergamo n Press , Oxford , 1969 .P.2 4

32 . G . Wfehnej: , "Th e Importanc e o f Reportabl e Event s i n th e Publi c Accep
tance" , p p i n Proceeding s o f th e Sevent hInternationa l Symposiumo n Packagin g and Transportatio n o f Radioactiv e Materials , Ne wOrleans , La. , Ma y15-20 , 1983 . 33 . G.E . Swindell , Privat e communicatio n Feb . 16 , 1983 . 34 . P.M . 3ryant , "Method s o f Estimatio n o f th e Dispersio n o f Windborn e Materia l an

d Dat a t o Assis t i n thei r Application , UXAE ARepor t AHSB(RP)R42 , 1964 . 35 . D.J . Gorman , "Consequence s o f a Transportatio n Acciden t Involvin g a

Larg e Quantit yo f Tritiate d HeavyWater" , Ontari o Hydr o Repor t HPD-76.7 , 1976 . 36 . G.J . Dicke , "Assessmen t o f Radiatio n Ris k i n th e Cas e o f Accident s wit h Truc k Transportatio n o f Tritiate d Wate r i n Drums" , Ontari o Hydr o Repor t RMEP-IR-790-R , 1980 . 37 . G.J . Dicke , " ARevie wo f th e Q Syste ma s Applie d t o th e Saf e Transpor t o f Tritiate d Water" , Ontari o Hydr o Repor t RMEP-IR-03457-1 , 1982 .

- 1 9 -APPENDI XA Participant s i n th e IAE ASpecia l Workin g Grou p Meetin g hel d i n London , 3 1 Augus t - 2 Septembe r 198 2 P.2 5

Chairman : Rawl , R . Workin g Grou

p Members : BELGIUM Baekelandt , L . CANADA Jack , G.C . Dicke , G.J .
DENMARK Ulbak , K . FRANC E Hamard , J . Grenier , M . Ringot , C . GERMANY , FEDERAL REPUBLI C Kolb , W.A .
ITAL Y Piermattei , Mrs . S . Faloci , C . JAPA N Kuwashima , K . Akaishi , J . Offic e o f Hazardou s Material s Regulatio n U S Departmen t o f Transport , Washingto n DC .

Ministr yo f Publi c Health , Brussel s

Atomi c EnergyContro l Board , Ottawa . Radioactivit yManagemen t and Environmenta l Protection , Ontari o Hydro , Toronto .
Nationa l Institut e o f Radiatio n Hygiene , Bronsho j

Commissaria t a l'Energi e Atomique , CE NFontenay-aux-Roses/Seine . Commissaria t a l'Energi e Atomique , CE NFontenay-aux-Roses/Seine . Commissaria t a l'Energi e Atomique , CE NFontenay-aux-Roses/Seine . 

### OF Physikalisch-Technisch e Bundesandstalt , Braunschweig .
Comitat o Nazional e pe r l'Energi a Nucleare , Rome . Comitat o Nazional e pe r l'Energi a Nucleare , Rom e

Nuclea r Transpor t Service s Co . Ltd . Toky o 

### Toka iResearc hEstablishment , JAERI , Ibaragi-ken
.

- 2 0 -P.2 6

SWEDE N- Pettersson , B . Svahn , Ms- . B .
UNITE D KINGDO M Blackman , D.J . Goldfinch , E.P . Macdonald , H.F . Shaw , K.B .
UNITE D STATE S O F AMERIC A Hopkins , D.R . Eckermann , K . Swedis hNuclea r Powe r Inspectorate , Stockholm . Nationa l Institut e o f Radiatio n Protection , Stockholm .
Departmen t o f Transport , London . Centra l Electricit yGeneratin g Board , London . Centra l Electricit yGeneratin g Board , Berkeley , Glos . Nationa l Radiologica l Protectio n 3oard , Chilton , Oxon .

U.S . Nuclea r Regulator yCommission , Washingto n DC . Oa k Ridg e Nationa l Laboratories , Tennessee . INTERNATIONAL MARITIM E ORGANISATION Wardelmann , Capt . H . Marin e Safet yDivision , Londo n Scientifi c Secretary : Barker , R.F . Departmen t o f Nuclea r Energyand Safety , Internationa l Atomi c EnergyAgency , Vienna , Austria .

- 2 1 -P.2 7

APPENDI XB Intak e Factor s fo r Typ e APackag e Transpor t Accident s
I n thi s Appendi xthe fractio n o f th e content s o f a Typ e Apackag e whic h mayb e release d an d inhale d b

yperson s i n the vicinit yo f a n acciden t i s

- 3 considered . I n th e 197 3 Regulation s i t wa s assume d tha t 1 0 o f th e packag e

_ 3 content s migh t escap e a s a resul t o f a "median " acciden t and tha t 1 0 o f thi s materia l migh t b e take n int o th e bodyo f a perso n involve d i n the acciden t [2] . Thi s result s i n a net t intak e facto r o f 1 0 o f th e packag e content s and , following discussion s at
- the Londo n SW GMeeting , thi s valu e ha s bee n retaine d withi n th e Q system . However , i t i s no wrecognise d a s representin g a rang e o f possibl e releas e fraction s and uptak e factors , a s discusse d i n th e mai n tex t o f thi s report , an d i t i s convenien t t o conside r intak e factor s i n term s o f thes e two parameter s independently . Th e rang e o f releas e fraction s no wrecognise d unde r th e Q system , namel y

- 3 - 2 1 0 - 1 0 , cover s tha t represente d b yth e earlie r assumptio n i n th e 197 3 Regulation s and th e origina l proposa l withi n th e Q syste m[3 , 4] . Underlyin g thi s ther e i s tha taci t assumption , als o containe d i n th e 197 3 Regulations , tha t th e likelihoo d o f a "majo r accident " whic hcoul d caus e th e escap e o f a larg e par t o f the packag e content s i s smal l [2] . T o a larg e exten t thi s approac hi s born e ou t b yth e behaviou r o f Typ e Apackage s i n sever e acciden t environment s [28-30] . Dat a o n th e respirabl e aeroso l fraction s produce d unde r acciden t con dition s ar e generall yspars e and onl yavailabl e fo r a limite d rang e o f materials . Fo r example , fo r uraniumand plutoniumspecimen s unde r enhance d oxidatio n rat e condition s i n ai r and carbo n dioxid e respirabl e aeroso l fraction s u

p t o M % hav e bee n reporte d [31] , However , belo wthi s leve l th e aeroso l fraction s showe d wid e variation s dependen t o n th e temperature s an d loca l atmospheri c flo wcondition s involved . I n th e cas e o f liquid s highe r fractiona l release s ar e obviousl ypossibl e bu t her e the multipl e barrier s provide d bythe Typ e Apackag e materials , including absorben t and lead shieldin g pot , remai n a n effectiv e containmen t syste meve n following sever e impac t o r crushin g accident s [30] . Indee d i n a recentl ycite d exampl e o f a n 13 1 I sourc e whic hwa s completel ycrushe d i n a highwa yaccident , les s tha n 2 % o f th e packag e content s remaine d o n th e road afte r remova l o f th e packag e debri s [32] .

- -? ? -P.2 8

Potentiall ythe mos t sever e acciden t environmen t fo r man yTyp e A package s i s th e combinatio n o f sever e mechanica l damag e wit ha fire . However , eve n i n thi s situatio n the rol e o f debri s mayb e significan t i n retaining release d activity , a s appeare d t o happe n i n the 197 9 Athen s DC 8 aircraf t acciden t [29 , 30] . Frequentl yfire s ten d t o produc e relativel ylarg e par ticulat e materia l whic hwoul d ten d t o minimis e an

yintak e vi a inhalation , whil e a t the same time providin g a significan t surfac e are a fo r the absorp

tio n o f volatil e specie s an d particularl yvaporise d liquids . Afurthe r molifying facto r i s the enhance d loca l dispersio n associate d wit hthe con vectiv e ai r current s du e t o the fir e whic hwoul d als o ten d t o reduc e intak e vi a inhalation . Base d o n consideration s o f th e typ e outline d her e a releas e fractio n

-2- 3 . . i n th e rang e 1 0 - 1 0 wa s agree d byth e SW Gmeetin g a s appropriat e fo r th e determinatio n o f Typ e Apackag e content s limit s withi n th e IAE ATranspor t Regulations . -4- 3 . . Th e 1 0 - 1 0 rang e o f uptak e factor s no wuse d withi n th e Q syste m i s base d upo n consideratio n o f a rang e o f possibl e acciden t situations , bot h indoor s an

d out-of-doors . Th e origina l Q syste mproposal s considere d 3 exposur e withi n a storeroo mo r carg o handlin g bayo f 30 0 mvolum e wit h4 roomai r change s pe r hour . Assumin g a n adul t breathin g rat e o f

— 4 3— 1 . - 3 3.3x1 0 ms thi s result s i n a n uptak e facto r o f M 0 fo r a 3 0 minut e exposur e period . A n alternativ e acciden t scenari o migh t involv e exposur e i n

3 a transpor t vehicl e o f 5 0 mvolum e wit h1 0 ai r change s pe r hour , a s employe d i n th e determinatio n o f th e Typ e B packag e norma l transpor t leakag e limi t i n th e 197 3 Regulation s [33] . Usin g th e same breathin g rat e and exposur e perio d

- 3 a s abov e thi s lead s t o a n uptak e facto r o f 2.4x1 0 , o f th e same orde r a s th e valu e obtaine d above . Fo r accident s occurrin g out-of-door s the mos t conservativ e assumptio n fo r the atmospheri c dispersio n o f release d materia l i s tha t o f a ground leve l poin t source . Tabulate d dilutio n factor s fo r thi s situatio n a t a downwind

- 4 - 2 - 3 distanc e o f 10 0 metre s rang e from7x1 0 t o 1.7x1 0 s. m[34] , corres pondin g t o uptak e factor s i n th e rang e 2.3x1 0 - 5.6x1 0 fo r the adul t breathin g rat e cite d above . Thes e value s appl yt o shor t termrelease s and cove r th e rang e fromhighl yunstabl e categoryAt o highl ystabl e categor yF weathe r conditions ; the correspondin g valu e fo r averag e categoryC/ D con dition s i s 3.3x1 0 , toward s th e lowe r en d o f th e rang e quote d above .

- 2 3 -P.2 9

Extrapolatio n o f th e model s use d t o evaluat e th e atmospheri c dilutio n factor s use d her e t o shorte r downwind distance s i s unreliable , bu t reducing th e exposur e distanc e b ya n orde r o f magnitud e t o 1 0 metre s woul d increas e the abov e uptak e factor s b yabou t a facto r o f 30 . Thi s i s indicativ e tha t a s the downwind distanc e approache s a fewmetre s th e uptak e factor s woul d approac h -4- 3 • • the 1 0 - 1 0 rang e use d withi n the Q system . However , unde r thes e circumstance s othe r factor s whic hwoul d ten d t o reduc e the activit yuptak e come int o effec t and mayeve n becom e dominant . Th e additiona l turbulenc e t o b e expecte d i n th e presenc e o f a fir e ha s bee n mentione d earlier . Simila r reduction s i n airborn e concentration s ca n b e anticipate d du e t o turbulenc e originatin g fromthe flo wo f ai r around an yvehicle s involve d i n a n acciden t o r fro m th e effect s o f nearb ybuildings .

- 4 - 3 Thu s o n balanc e i t i s see n tha t uptak e factor s i n th e rang e 1 0 - 1 0 appea r reasonabl e fo r th e determinatio n o f Typ e Apackag e content s limits . Take n i n conjunctio n wit hth e releas e fraction s discusse d earlier , the yresul t i n th e overal l intak e facto r o f 1 0 agree d byth e Londo n SW Gmeeting .P.3 0

APPENDI XC Concentratio n Limit s fo r Consignment s o f TritiumTransporte d i n Typ e APackage s
A s note d i n th e mai n tex t o f thi s report , tritiu man d it s compound s ar e the subjec t o f specia l consideratio n unde r the Q system . Thi s arise s becasu e the majorit yo f transpor t requirement s fo r tritiu mar e i n the for

mo f tritiate d wate r and , i n addition , tritiate d wate r i s likel yt o b e forme d durin g th e transpor t o r storag e o f tritiu mga s o r othe r compound s o f tritium . Fo r thes e reason s the remainin g discussion s her e relat e t o tritiate d water , althoughi t shoul d b e note d tha t a facto r o f 5 0 reductio n i s applicabl e i n the specia l cas e o f organi c form s o f tritiu m[10] . I n al l case s th e Q value s determine d fo r tritiu mexcee d the arbitrary 4 0 TB qcut-of f limit , cf . Q D> 37 0 TBq , Q

_= 300 0 TB qfo r tritiate d wate r and Q „ = 6 0 TB qfo r organi c form s o f tritium . Sinc e Typ e Apackage s designe d fo r th e transpor t o f liquid s ar e require d t o hav e doubl e containmen t o r absorben t materia l and t o withstand a 9 metr e dro p test , th e assumptio n o f a releas e i n th e rang e 0.1-1 % use d i n th e derivatio n o f Q i s no t unreasonable , Indee d a t th e Londo n SW Gmeetin g th e vie wwa s expresse d tha t i t migh t b e undul yconservativ e i n manypractica l acciden t situations . I t i s inappropriat e t o calculat e a Q

_ valu e fo r tritiumsinc e th e radiatio n dos e t o th e sensitiv e basa l laye r o f th e ski n woul d b e insignifi

can t fo r thi s lowenergybet a emitter . However , contaminatio n o f th e ski n lead s t o two potentia l interna l exposur e routes , namel yingestio n o r adsorptio n throughthe skin , and thes e resul t i n a specifi c activit ylimita

tio n fo r tritiate d wate r transporte d i n a Typ e Apackage . Th e consideration s outline d abov e concernin g th e integrit yo f suc hpackage s mak e extensiv e wettin g o f th e ski n unlikel yan d i n th e treatmen t presente d her e i t i s assume d tha t onl yth e hand s ar e involved ; thi s follow s th e origina l proposal s fo r th e derivatio n o f tritiu mlimit s withi n th e Q syste m[4] . I f the specifi c activit ylimi t fo r tritiu mi s define d a s C Bq. l , thi s mayb e determine d i n term s o f th e dos e commitment s du e t o absorptio n throughthe skin , D , an d tha t vi a ingestion , D_ . Th e forme r i s give n b y [35] : D = 19 0 { 1 + 0. 2 xt' } xf xC/10 0 x3. 7 x10 1 °

= 5.1 4 x10~ 1 1 { 1 + 0. 2 xt' } xf xC mSv ,P.3 1

wher e t ' i s the tritiate d wate r ski n contac t time i n minutes , and f i s the fractio n o f th e bodyski n wetted . Th e dos e vi a ingestio n mayb e estimate d o n

- 3 ? the assumptio n tha t a perso n mayinges t al l the tritiate d wate r from1 0 m " 9 (1 0 cm" ) o f skin , wit hthe thicknes s o f th e moistur e laye r o n th e hand s take n

_ / Q a s 1 0 m , and notin g tha t a n intak e o f on e AL I ( 3 x1 0 Bq ) result s i n a committe d effectiv e dos e equivalen t o f 5 0 mS v[10] . Thi s lead s to : D , = 5 0 x10" * xC/ 3 xIO 9

- P =1.67x1 0 ~x C mSv . Further , limiting th e tota l dose , D + D_. , t o 5 0 mS vand notin g tha t th e ski n 2 . 2 are a o f th e hand s i s 0.0 6 m " an d tha t o f th e whol e bodyi s 1.7 5 m[23] , and assumin g tha t th e ski n remain s wette d fo r a perio d o f u p t o on e hour , on e obtains : C = 2. 0 x10 1 2 Bq.l" 1 = 2 PBq.m" 3 (^5 0 Ci.l" 1 ) . An alterantiv e exposur e scenari o i s tha t involvin g a Typ e Apackag e involve d i n a fir e i n a confine d spac e i n whic hi t i s likel ytha t tritiate d wate r woul d evaporat e rapidly . Assumin g a n initia l ambien t temperatur e o f 38° C a t a relativ e humidit yo f 50% , th e evaporatio n i s likel yt o increas e th e relativ e humidit yt o M00% . Thi s woul d resul t i n a tritiate d moistur e conten t fo r

- 3 - 1 ai r a t 38° C o f 2 3 g. m[36] , leadin g t o a n intak e rat e o f 27. 3 g. hfo r a

- 4 3 - 1 perso n breathin g a t th e typica l adul t activ e rat e o f 3.3.1 0 m. s [23] . Thi s rat e woul d b e increase d b y50 % du e t o absorptio n throughth e ski n givin g a net t intak e rat e o f 41. 0 g. h. Further , i f i t i s assume d tha t a perso n i s unlikel yt o b e expose d unde r thes e condition s withou t breathin g protec
tio n fo r a perio d o f mor e tha n 3 0 minutes , th e maximumintak e o f tritiate d wate r i s 20. 5 g . Equatin g thi s intak e wit hth e AL I thu s lead s t o a specifi c activit ylimi t fo r tritiate d wate r a s follows : C = 3 xl0 9 /20. 5 Bq.g" 1
s 0.1 4 x10 1 2 Bq.l" 1 = 0.1 4 PBq.m" 3 ( ^ 4 Ci.l" 1 ) . Amor e detaile d treatmen t o f a simila r scenario , taking int o accoun t th e finit e evaporatio n rat e o f 20 0 litre s o f tritiate d wate r spil t ove r a floo r

2 are a o f 10 0 m[37] , lead s t o a somewha t highe r specifi c activit ylimi t o f

9 - 1 1.2 5 x10 ' Bq. g . Thi s resul t i s base d upo n us e o f th e long-termaverag e

- 4 3- 1 adul t breathin g rat e o f 2 x1 0 m. s , and us e o f th e highe r short-term

- 2 6 -P.3 2

rat e cite d abov e reduce s the calculate d specifi c activit ylimi t fo r tritiate d wate r t o 0.77'*Bq.g~ 1 o r 0.7 7 PBq.m" 3 (^2 0 Ci.l" 1 ) . Finally , detaile d assessment s o f the likel yrelease s o f tritiate d wate r unde r acciden t condition s fromstrong industria l container s use d fo r road transpor t hav e bee n carrie d ou t [36] . Thes e studie s considere d the probabilit y o f occurrenc e o f accident s o f varyin g severit yan d o f variou s meterologica l conditions . Theyshowe d tha t i n ^90 % o f accident s involving tritiate d wate r o f 2 0 Ci. l specifi c activit ycontaine d i n 5 5 gallo n typ e CTC-5 B drum s the resulting dos e commitment s t o expose d person s wer e 5 remo r less . Con
sideratio n o f the result s o f thi s study , noting tha t Typ e Apackage s ar e capabl e o f withstandin g condition s o f muc hgreate r severit ythan strong industria l package s and th e case s considere d earlier , led t o th e Londo n SW G meetin g recommendin g a Typ e Apackag e specifi c activit ylimi t fo r consign

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TABL E I (Continued )
Radio

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D r E D r D D r J M r D M r M M r H M r H D r M r G J

M r 

### Dr D r T Broom Actin g LaboratoryManage r D r P F Cheste r WCarpente r J Silverlea f K Wrigh t WC Bake r E Peplo w F J Hadril l GMasterso n Oate s Brown M r B V Georg e D r B Edmondso n D r RS Hal l M r MV Speigh t D r J E Antil l H ATownle y E GMeredit h D r K H Jolliff e Researc hPlannin g Office r M r J C Metcalf e D r S Blo w M r F Broomhea d Report s Libraria n Libraria n Libraria n Libraria n Libraria n Libraria n Libraria n Libraria n Libraria n Technica l Serv . Manage r Libraria n M s C AStot t Libraria n Libraria n Libraria n Libraria n Libraria n Libraria n D r P MKell y Goldfinc h Rudma n J Ke e L Moor e S L Danfor d RMatthew s C Dal e M r M r M r M r M r M r M r E R F E D R G M r R B Peppe r Berkele yNuclea r Laboratorie s Headquarter s Headquarter s S E Regio n SWRegio n Midland s Regio n NE Regio n N WRegio n Generatio n Developmen t & Constructio n Div . Generatio n Developmen t & Constructio n Div . Nuclea r Ops . Suppor t Group Berkele yNuclea r Laboratorie s • Berkele yNuclea r Laboratorie s Berkele yNuclea r Laboratorie s Berkele yNuclea r Laboratorie s Berkele yNuclea r Laboratorie s Centra l Electricit yResearc hLaboratorie s Marchwoo d Engineerin g Laboratorie s Marchwoo d Engineerin g Laboratorie s Headquarter s Headquarter s (2 ) Headquarter s Berkele yNuclea r Laboratorie s Centra l Electricit yResearc hLaboratorie s Marchwoo d Engineerin g Laboratorie s SS D Midland s Regio n SS D S E Regio n SS D N E Regio n SS D N WRegio n SS D SWRegio n SSEB , Eas t Kilbrid e SSE B UKAEA , Risle y AECL , Chal k River , Canad a AECL , Whiteshell , Canad a CEN , Saclay , Franc e Centr o Informazion i Stud i Esperienze , Ital y Studsvi k Energitekni k AB , Swede n ECN , Petten , Netherland s AAEC , Luca s Height s NTP , Ashfor d Ken t (2 ) EPRI , California , US A Ontari o Hydro , Canad a TVA , Chattanooga , US A TPR D Headquarter s (Chin a NPIC ) Healt h& Safet yDepartmen t Healt h& Safet yDepartmen t Healt h& Safet yDepartmen tP.4 9

TPRD/B/O340/R8 3 

### Mr Mr S Dr S M r 

### Mr M r M r Mr Mr D r M r M r Mr M r Mr M r Mr Mr Mr D r M r M r Mr M r Mr Mr Mr Mr M r Mr Mr 

### E G J J J F G G D J B A M N K K P J P C H L F K W A P P M H J P Goldfinc h F Heap ABonn e 1 1 Collie r D Har t H Passan t H Jone s B Mummer y B Gothar d Bishto n WWillco x Pau l MWasso n B Owen s H Gardne r GSteel e F Heato n F Outra m ACarte r Smitto n C Tresis e Bea r Bentle y S Whit e MWilliam s RKirkpatric k RJone s RParkma n Gree n GRJone s Westmorelan d Statio n Manage r 

### Mr Mr Mr 

### N G G GWallac e Jackso n Featherston e Libraria n Libraria n Libraria n Libraria n Libraria n Libraria n Libraria n Libraria n 

### Mr Mr Mr S D r S M r 

### D r 

### D r Dr D r Dr 

### R D M G D K R J B H L Gardine r WFleetwoo d S Stag g C Alle n V Frec k ASimpso n J Pearc e ACroft s MWhea t le

y F Macdonal d (20 ) Healt h& Safet yDepartmen t Healt h& Safet yDepartmen t Healt h& Safet yDepartmen t Generatio n Developmer t & Constructio n Div . Generatio n Developmer t & Constructio n Div . Generatio n Developmer t & Constructio n Div . Generatio n Developmer t & Constructio n Div . Nuclea r Ops . Suppor t Group Nuclea r Ops . Suppor t Group Berkele yPowe r Statio n Berkele yPowe r Statio n Bradwel l Powe r Statio n Bradwel l Powe r Statio n Dungenes s 'A ' Powe r Statio n Dungenes s 'A ' Powe r Statio n Dungenes s 'B ' Powe r Statio n Dungenes s 'B ' Powe r Statio n Hinkle yPoin t Powe r Statio n Hinkle yPoin t Powe r Statio n Oldbury-on-Sever n Powe r Statio n Oldbury-on-Sever n Powe r Statio n Sizewel l Powe r Statio n Sizewel l Powe r Statio n Trawsfynyd d Powe r Statio n Trawsfynyd d Powe r Statio n Wylf a Powe r Statio n Wylf a Powe r Statio n Hartlepoo l Powe r Statio n Hartlepoo l Powe r Statio n HeyshamPowe r Statio n HeyshamPowe r Statio n SSE B Huntersto n 'A ' Powe r Statio n SSE B Huntersto n 'B ' Powe r Statio n SSE B Huntersto n Powe r Statio n SSE B Huntersto n Powe r Statio n UKAE AHarwel l UKAE ASpringfield s UKAE ADounreay UKAE AWindscal e (2 ) UKAE AWinfrit h UKAE ARisle y NRP B Harwel l BNF L Windscal e Berkele yNuclea r Laboratorie s Berkele yNuclea r Laboratorie s Berkele yNuclea r Laboratorie s Berkele yNuclea r Laboratorie s Berkele yNuclea r Laboratorie s Berkele yNuclea r Laboratorie s Berkele yNuclea r Laboratorie s Berkele yNuclea r Laboratorie s Berkele yNuclea r Laboratorie s (15 ) Berkele yNuclea r Laboratorie sP.5 0

TPRD/B/0340/R8 3


### D r Mr D r D r D r D r D r M r Mr Mr Mr M r Mr M r M J P J P G S A I P R R D R WCharle s RHarve y J Darley 0 Corbet t RMau l AHart e Nai r Pantin g MGThompso n J Ballar d Dutc h A0'Sulliva n J Blackma n Raw l
M r L Baekeland t M r GJ Dick e M r GC Jac k M r K Ulba k
M r J Hamar d M r MGrenie r M r C Ringo t
Prof . D r WAKol b Mr s S Piermatte i M r C Falcon i D r K Kawashima
D r J Akaish i 

### M r B Pettersso n M s B Svah n Berkele yNuclea r Laboratorie s Berkele yNuclea r

Laboratorie s Berkele yNuclea r

Laboratorie s Berkele yNuclea r

Laboratorie s Berkele yNuclea r

Laboratorie s Berkele yNuclea r

Laboratorie s Berkele yNuclea r

Laboratorie s Berkele yNuclea r

Laboratorie s Berkele yNuclea r

Laboratorie s Berkele yNuclea r

Laboratorie s (2 ) Oldbur yNuclea r

Power Trainin g Centr e Dept
. o f Transport , 2MarshamStreet , Londo nSW1

P3E B Dept
. o f Transport , 2MarshamStreet , Londo nSWI

P3E B Offic eo f

Harzardou s Material s Regulation , U.S
. Dept
. of.Transport , Washingto n DC20590US

A Ministr yo f

Publi c Health , 3 0ru e Josep hII , B-104 0Brussels , Belgiu m Ontari o Hydro , 59 5 Ba yStreet , Toronto , Ontario , Canad a• Atomi c Energ yContro lBoard , P O Box1046 , Ottaw aKI

P5S 9 Canad a Nat
. Inst , o f

Radiatio nHygiene , Frederikssundsve378 , DK-2700 0 Bronshoj , - Denmar

k Centr ed'etude s nucl€aire , B.P.6. , Fontenay-aux-Roses , Paris , Franc e Commissaria t

al'energi enucleaire , Centr ed'entude s nucleaire , B.P.6
. Fontenay-aux-Roses , Paris , Franc e Commissaria t

al'energi enucleaire , Centr ed'etude s nucleaire , B.P.6
. PTB , Bundesalle e100 , D-330 0 Braunschweig , WGermany CNEN , Vial eRegin aMargherit a125 , 1-00198 , Rome , Ital y CNEN , Vial eRegin aMargherit a125 , 1-00198 , Rome , Ital y Nuclea r Transpor t

Service s C

o Ltd , 1-1- 3 Shibadaima nMinato-ku , Tokyo , Japa n Toka iResearc hEstablishment , JAERI , 2- 4 Shirakatashirane , Tokai-mur a Naka-gun , Ibaragi-ken , Japa n Swedis hNuclea r

Power Inspectorate , Box2 7 106 , S-10 2 5 2Stockholm , Sweden Nat
. Inst , o f

Radiatio nProtection , Bo x6 0204 , 5-10 4 0 1 Stockholm , SwedenP.5 1

TPRD/B/0340/R8 3 M r K B Sha w M r D RHopkin s M r K Eckermann
M r RB Pop e
M r GE Swindel l 

### (2 ) NRPB , Chilton , Didcot , Oxa n 0X1 1 OR Q Offic e o f Research , U S Nuclea r Regulatory Commission , Washingto n DC 20555 , US A Healt hSafet yResearc hDivision , Oak Ridg eNationa lLabs. , Oak Ridge , Tennesse e 37830 , US A Dept . o f Nuclea r Energyan d Safety , IAEA , Wagramerstrass e 5 , P O Bo x100 , A-140 0Vienna , Austri a 3 3 Tetbur yStreet , Minchinhampton , Glo s GL 6 9J HP.5 2



## REPOR TSUMMAR YSHEE T Centra l Electricit yGeneratin g Boar d Berkele yNuclea rLaboratorie s

TPRD/B/0340/R8 3 Jo bNo . XB25 5 Th e Q Syste mfo r th e Calculatio n o f Aand A
- Value s withi n th e IAE ARegulation s fo r th e Saf e Transpor t

o f Radioactiv e Material s

- b y- H.F . Macdonal d an d E.P . Goldfinch * Septembe r 198 3 SUMMARY Thi s repor t contain s a comprehensiv e descriptio n o f th e Q system , a n improve d metho d fo r evaluatin g th e Typ e Apackag e content s limi t A ^ an d A 2 value s withi n th e IAE ARegulation s fo r th e Saf e Transpor t o f Radioactiv e Materials . Th e wor k reporte d her e wa s performe d i n collaboratio n wit hth e Board' s Healt hand Safet yDepartmen t unde r th e term s o f Researc hAgreemen t No . 2291/CF , whic hform s par t o f th e IAE ACoordinate d Reseac hProgramm e o n th e Saf e Transpor t o f Radioactiv e Materials . Th e Q syste mwa s adopte d b yth e IAE Ai n Marc h198 2 fo r th e calculatio n o f A- | and A 2 value s t o b e publishe d i n th e 198 4 revise d editio n o f th e Transpor t Regulations . Thi s presen t repor t wa s prepare d a t th e reques t o f th e Agenc yfo r publicatio n a t th e sam e tim e a s th e revise d regulation s late r nex t year . Fo r thi s reaso n th e forma t use d i s somewha t differen t fro mtha t o f standar d TPR D reports , followin g instea d tha t use d byth e Agenc yi n it s publications . Th e Q syste mrepresent s a developmen t an d extensio n o f th e earlie r A-|/A 2 system . I t incorporate s th e lates t recommendation s o f th e ICR P and , b yexplicitl yidentifyin g th e dosimetri c consideration s underlyin g th e derivatio n o f Typ e Apackag e content s limits , provide s a firme r and mor e defensibl e basi s fo r th e IAE ATranspor t Regulations . Overal l th e us e o f th e Q syste mintroduce s relativel ymino r variation s i n th e A^ an d A 2 value s compare d wit hthos e i n th e 197 3 Editio n o f th e Regulations . Wher e majo r variation s occur , saybya facto r o f greate r tha n 2-3 , thes e ar e generall y associate d wit hreduction s i n th e Typ e Apackag e content s limit s fo r bet a emitter s determine d bydosimetri c pathway s no t previousl yconsidered . Isolate d relaxation s i n th e content s limit s als o occu r du e t o change s i n dosimetri c dat a introduce d i n ICR P Publicatio n 3 0 and mor e generall yi n th e cas e o f specia l formalph a emitter s du e t o th e revise d definitio n o f th e Ai valu e fo r suc hmaterials . Content s Approve d
Date : Classificatio n an d Distributio n Approve d X^l",
_ Date : /