OF FWNCTIQ GAMMA-RAY BUILDUP F

119
A SURVEY OF EMPIRICAL FWNCTIQ FIT GAMMA-RAY BUILDUP F D. K. Trubey s I TI c E

Transcript of OF FWNCTIQ GAMMA-RAY BUILDUP F

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A SURVEY OF EMPIRICAL FWNCTIQ FIT GAMMA-RAY BUILDUP F

D. K. Trubey

s I TI c E

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RADlATlON SHIELD3NG INFORMATION CENTER

P.O. B o x x O a k R i d g e , T e n n e s s e e

O A K R I D G E N A T I O N A L L A B O R A T O R Y

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ORNL-RSIC- 10

C o n t r a c t N o . W-71405-eng-26

Neutron Fhysics D i v i s i o n

A SURVEY OF EMPIRICAL FUNCTIONS USED TO

F I T GAMMA-RAY BUILDUP FACTORS

D . K. Trubejr

FEBRUARY 1 96 6

OAK RIDGE NATIONAL LABORATORY Oak R i d g e , Tennessee

operated by UNION CARBIDE CORPORATION

f o r the U S ATOMIC EIERGY COI4MISSION

3 4 4 S b 51323335 4

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iii I .

TABLl3 OF CONTENTS

PAGE

I n d e x t o T a b l e s . . . . . . . . . . . . . . . . . . . . . . . . . . V

I n d e x t o F i g u r e s . . . . . . . . . . . . . . . . . . . . . . . . . v i i

Abstract . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1

PART I - Review of Empirical Buildup Fac:;or. Functions . . . . . . . 1

Int roduct ion . . . . . . . . . . . . . . . . . . . . . . . . . . 1

Linear Form . . . . . . . . . . . . . . . . . . . . . . . . . . 2

Taylor Form . . . . . . . . . . . . . . . . . . . . . . . . . . 3

Polynomial Form 3 Berger F o r m . . . . . . . . . . . . . . . . . . . . . . . . . . . 4

Parameters f o r Linear and Quadratic: Forms . . . . . . . . . . . . 5

Ot'ner Forms . . . . . . . . . . . . . . . . . . . . . . . . . . . 5

. . . . . . . . . . . . . . . . . . . . . . . . .

Graphical Coinparison . . . . . . . . . . . . . . . . . . . . . . a S t a t i s t i c a l Comparison of Taylor and Herger Forms . . . . . . . . . . . . . . . . . . . . . . . . and Conclusioris 9

Applicat ion of Buildup Fac to r s for Dis t r ibu ted Sources in Plane Geometry . . . . . . . . . . . . . . . . . . . . . . . . 84

Plane I s o t r o p i c Source Kernel Using Berger Formu1.a . . . . . . . 84

I n t e g r a t i o n of Plane Kernel with Exponential Source Dis t r ibu-

PART I1 -

tion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 85 Uncollided Dose R a t e . . . . . . . . . . . . . . . . . . . . . . 87

Sca t t e red Dose Rate . . . . . . . . . . . . . . . . . . . . . . . 9 l

Graphed Functioris for Dis t r ibu ted Plane Sources . . . . . . . . . g j

Larnj-nated Media 103 Acknowledgement . . . . . . . . . . . . . . . . . . . . . . . . . . 1-03

References . . . . . . . . . . . . . . . . . . . . . . . . . . . . 104

PART I11 - Applicat ion of EhLri.ldup Fac tors i n F i n i t e or . . . . . . . . . . . . . . . . . . . . . . . .

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INDEX TO TABUS

Buscaglione-Manzini Coeff ic ien ts f o r Taylor Dose Buildup

Fac tor Forrnula . . . . . . . . . . . . . . . . . . . . . Buscaglione-Manzini Coef f i c i en t s for Taylor Energy Buil dup

Factor Formula . . . . . . . . . . . . . . . . . . . . .

. .

. . Buscaglione-Manzin-i~~ Coef f i c i en t s for Taylor Energy Absorption

Buildup Factor Formula . . . . . . . . . . . . . . . . . . . Buscaglione-Manzinj. Polynomial Coef f i c i en t s f o r the Dose

Buildup Fac tor i n Various Concretes . . . . . . . . . . . . Linear, Quadrat ic and Berger Coeff ic ien ts f o r Dose Buildup

Fomiil.as F i t t e d over t h e Range (0-7 MFP) . . . . . . . . . . Linear, Quadra t ic and Berger c o e f f i c i e n t s f o r Energy Absorp-

t i o n Buildixp Formulas F i t t e d over the Range (0-7 WP)

Linear, Quadra t ic and Berger Coef f i c i en t s f o r Dose Buildup

. . .

Forinulas F i t t e d over the Range (0-20 MFP) . . . . . . . . . Linear, Quadratic and Berger Coef f i c i en t s f o r Enerm Absorp-

t i o n Buil.dup Formidas F i t t e d over t h e Range (0-20 MF'P) . . . Comparison of Average Percentage Deviat ion Using Berger

and Tayl.or. Dose Foraiul.as . . . . . . . . . . . . . . . . . .

PAGE

46-49

50- 52

53

54

55-64

65-68

69-78

79-82

83

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INDEX TO FIGURES

L

1. Berger Factor C a s a Function of Energy for Various Mate- r i a l s . . . . . . . . . . . . . . . . . . . . . . . . . .

2 . Berger Fac tor D as a Funct.Lon of Energy f o r Various Mate- r i a l s . . . . . . . . . . . . . . . . . . . . . . . . . .

3 . Comparisoil of Linear, Quadratic, a i d Berger Dose Buildup Fac tors i n Water (0.25 MeV, 20 MFP) . . . . . . . . . . .

4. Compirison of Linear, Quadratic, and Berger Dose Duildup Fac tors i n Water (0.25 MeV, 7 WP) . . . . . . . . . . .

5. Comparison of Polynomial and 13erger Dose Buildup Fac tors i n Water (0.25 MeV, 20 MFP) . . . . . . . . . . . . . . .

6. Comparison of Polynomial and Berger Dose Buildup Fac tors i n Water (0.25 MeV, 7 MFP) . . . . . . . . . . . . . . .

7 . Comparison of Linear , Quadratic, and Eerger Dose Buildup FacLors in Water (0.5 MeV, 20 ?FP) . . . . . . . . . . .

8 . Comparison of Taylor arid Berger Dose Buildup Fac tors i.n Water (0.5 MeV, 20 l@P) . . . . . . . . . . . . . . . . .

9. Compnrison of Polynomial and 13erger Dose Buildup Fac tors i n Water (0.5 MeV, 20 MFP) . . . . . . . . . . . . . . . . .

10. Comparison of Linear, Gjuadratj-cy and Berger Dose Ruildup Factors i n Water (2 MeV, 20 l@P) . . . . . . . . . . . .

11. Comparison of Tayl-or a n d Berger Dose Buildup Fac tors i n Water (2 MeV, 20 Ki1p) . . . . . . . . . . . . . . . . . .

l2. Comparison of Polynomial and Berger Dose Buildup Fac tors i n Water (2 MeV, 20 MFP) . . . . . . . . . . . . . . . . . .

13. Comparison of Linear, Quadratic, and Rerger Energy Absorp- t i o n Buildup Fac to r s i n Water (6 MeV, 20 MFP) . . . . . .

14. Comparison of Tayl-or and Berger Energy Absorption Zhiildup Fac to r s i n Water (6 MeV, 20 MFP) . . . . . . . . . . . .

15. Comparison of Polynomial and Berger Energy Absorption Buildup Fac tors i n Water (6 MeV, 20 MFP) . . . . . . . .

16. Cornparison of L i r i e w , Quadratic, and Berger Dose Buildup Fac tors i n AI-uminum (6 MeV, 20 NFP) . . . . . . . . . . .

17. Comparison of Tayl-or and Berger Dose _Buildup Fac tors i n Aluminum (6 MeV, 20 MFP) . . . . . . . . . . . . . . . .

PAGE

6

18

13

20

2 1.

22

23

24

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25 18. Comparison of PoI.ynornia1 and Berger Dose Buildup Fac to r s

i n ALuminum (6 M ~ V , 20 MFP) . . . . . . . . . . . . . . . Comparison of Linear, Quadrat ic , and- Berger Dose Buildup

Fac to r s i n Lead (0 .5 MeV, 20 PPP) . . . . . . . . . . . . 19

20.

26

Comparison of Linear, Quadrati-c, and Berger Dose Buildup Fac to r s i n Lead (3 MeV, 20 W P ) . . . . . . . . . . . . . 27

28 21.. Comparison of Taylor and Berger Dose Buildup Fac to r s i.n

Lead. (3 MeV, 20 WP) . . . . . . . . . . . . . . . . . . 22. Comparison of Polynomial and Berger Dose Buildup Fac to r s i n . . . . . . . . . . . . . . . . . . Lead (3 MeV, 20 MFP) 29

23

211 .

Comparison of Linear, Quadratic, and Berger Dose 3uildup Fac to r s i n Lead (6 MeV, 20 MTP) . . . . . . . . . . . . .

Comparison o f Ta,ylor and Berger Dose Buildup Fac to r s i n Lead ( 6 M e V , 20MFP) . . . . . . . . . . . . . . . . . .

25. Comparj.sou? of Polynomial and Berger Dose Buildup Fac to r s i n Lead ( 4 M ~ V , 20 MFP) . . . . . . . . . . . . . . . . . 32

26. Comparison of Linear, Quadratic and Berger Dose BuiIdup Fac to r s i n Lead (10 MeV, 20 MFP) . . . . . . . . . . . . 33

34

35

36

3 7

38

39

40

4 1..

27 Comparison of Tayloi- and Berger Dose Buildup Fac to r s i.n Lead (10 MeV, 20 MFP) . . . . . . . . . . . . . . . . . .

28. Comparison of Polynomial and Berger Dose Bui-ld-up Fac to r s i n Lead (1 0 MeV, 20 MFP) . . . . . . . . . . . . . . . .

Comparison of Linear, Quad.ratic and Berger Dose Buildup Fac’iors i n k . a d (6 MeV, 7 MFP) . . . . . . . . . . . . .

30 Comparison of Linear, Quadratic and Berger Dose Buildup Fac to r s i n Lead (10 MeV, 7 M F 1 ) . . . . . . . . . . . . .

31 Comparison o r Linear, Quadratic and Berger Dose Buildup Fac to r s i n Ordinary Concrete (1 MeV, 20 MIEP) . . . . . .

Comyarison of Taylor and Berger Dose Buildup Fac to r s i n Ordinary Concrete (J- MeV, 20 ME’P) . . . . . . . . . . . . 32 *

33 *

34.

Comparison of Polynomial and Rerger Dose BuiI.dup Fac to r s i n Ordinary Concrete (1 MeV, 20 MF’P) . . . . . . . . . . . .

Compari-son of Linear, Quadratic, and Berger Dose Buildup Faxtors i n Ordinary Concrete (6 MeV, 20 WP) . . . . . .

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35.

36.

Comparison of Taylor and Berger Dose Buildup Fac to r s i n Ordi-

Comparison of Polynomial Dose Buildup Fac to r s i n Ordinary

nary C o n c r e k (6 MeV, 20 MFP) . . . . . . . . . . . . . . . 42

Concrete (6 MeV, 20 MFP) . . . . . . . . . . . . . . . . . 43

37. Corrtparison of Linear, Quadra-tic and Berger Dose Buil-dup Fac to r i n Lead (6 MeV, 7 MFP) . . . . . . . . . . . . . . . 4 J4

38. Comparison of Linear, Quadra t i c aid Berger Energy Absorp- t i o n ~ u i l d u p F a c t o r s i n k a i i (0.5 MeV, 7 MFP) . . . . . . . 45

39. Geometry of Integrat i -on Over Exponential. Soiirce Di s t r ibu - t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . 86

40. The Slab Function I& (x ,a) for Values of a Between 0 and 3 . . 97

)+le The Slab Fimction (x ,a) for Values of a Between 0 and 3 . . 98

42" The I n f i n i t e Medium Function & (x ,a) f o r Values of a . . . . . . . . . . . . . . . . . . . . . . Between 0 and 3 99

1+3. The I n f i n i t e Medium Function ( x p ) f o r Values of Q! Between 0 and 3 . . . . . . . . . . . . . . . . . . . . . . 100

44. 'me I n f i n i t e M e d i u m Function b ( x , a ) f o r Values of CZI Between 0 and 3 . . . . . . . . . . . . . . . . . . . . . . 1.01.

45. The I n f i n i t e Medium Function (x,CZI) f o r Values of a B e h e e n 0 and 3 . . . . . . . . . . . . . . . . . . . . . . 102

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A SURVEY OF EMPIRICAL FUMCTIONS USED '70

FIT GAMMA-RAY BUILDUP FACTORS

D . K. Trubey

ABSTRACT

'The use of simple f u n c t i o n s t o es.Lirnate gamma-ray bui ldup f a c t o r s i s reviewed on the basis of simpl.icity and a,ccuracy. Anal-ysis shows t h a t t h e b e s t f j - t t i n g form i s t h e 4 term poly- nomial f i t wit'n c o e f f i c i e n t s publ ished by Capo. For m o s t pur- poses, however, a, f u n c t i o n proposed by Berger i s Yecoinmended s i n c e it i s as sirlrple to use as the ].inear form and i s essen- t i a l l y as good as t h e more complicated forms.

Tables of the c o e f f i c i e n t s a r e given f o r t h e I- inesr , qua,d- r a t i c , Berger, arid Taylor f i t t i n g fur tc t ions. Some t y p i c a l graphs of t h e funct ior is axe also given.

f o r t h e case of exponent,ial. source d - i s t r i b u t i o n s i n plane geometry and t h e use of bui ldup f a c t o r s i n f i n i t e geometry i s b r i e f l y descr ibed .

Use of -the Berger and. pcil.ynomin,l- func t ions i s demoristrated

PART 1 - Review OF Empir ical Lhiil-dup Fac to r Fiunctions

J n t z oduc t i o n

Ever s ince gam-a-ray a t t e n u a t i o n r e s u l t s i n simple geometry have

been a v a i l a b l e , t h e y have been used i n the form of bu i ldup fac to?-s .

The bui ldup f a c t o r s have been, and cont inue t o be, very usefu-1 s i n c e

cal.culati.ons making use of them are rela-Live1.y simple arid y i e l d Tela-

Live ly quick and, i n md,ny cases , accu ra t e r e s u l t s . A simple d e f i n i -

t i o n of t h e bui ldup f a c t o r i s t h e r a t i o of any d e s i r e d q u a n t i t y charac-

t e r i s t i c of t h e t o t a l gamma ray f l u x to the same q u a n t i t y c h a m c t e r i s t i c

of t h e unsca t t e red f lux. The two most useful. bui ldup fac-Lors are t h e dose

arid energy absorp t ion buil-dup f a c t o r s . Applying the above d e f i n i t i o n , the

dose bui ldup f a c t o r i s t h e r a t i o of t h e t o t a l . dose ( o r dose ra te ) a t a

g iven p o i n t i n a given tnedium t o t'ne dose (or dose r a t e ) a t that, p o i n t due

to tine unsca1;tered f l u x which i s g e n e r a l l y r e l a t i v e l y easy t o c a l c u l a t e .

The energy absorption. bu i ldup f a c t o r i s s i m i l a r l y def ined

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Most of t h e bui ldup f a c t o r s i n cu r ren t use a r e those publ ished by 1 .

Goldstein and Wj-lkins i n 1954. They g ive r e s u l t s i n i n f i n i t e media for

seven m a t e r i a l s and up t o nihe source ene rg ie s which cover t h e range of

i n - t e r e s t for r e a c t o r and weapons siiiel-ding. Results f o r o the r m a t e r i a l s

and ene rg ie s may be obtained by interpol-a.ti.on s i n c e tine bui ldup factors

a r e smooth func t ions of energy and. atomic number. They considered plane

co l l imated and. po in t i s o t r o p i c sources bu-t on ly t h e l a t t e r aye considered

i n thris r e p o r t .

TAnear Form

Probably t h e e a r l i e s t used formula f o r a bui ldup f a c t o r was t h e l i n e a r

form. That i s , t h e bui ldup f a c t o r i s given by

where

E I: source energy,

p = l i n e a r a t t e n u a t i o n c o e f f i c i e n t ,

H :I d i s t a n c e t o source .

Before r igorous r e s u l t s were a v a i l a b l e , t h e value of pi was assumed t o

be 1 although Goldstein2 pointcd out t h a t , i n t h e czse of t h e energy

absorpt iul i bui ldup f a c t o r , AI may be determined by t h e a p p l i c a t i o n of

tine conserva t ion of energy. Yndt i s , t h e energy of t he source i s set

equal t o absorp t ion i n t e g r a t e d over a l l space. Thus

where

B(pR) = 1 + %pR, =: l i n e a r energy absorp t ion c o e f f i c i e n t ,

ba

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which y i e l d s

4 =

The l inear- form has the advantage of being simple but (as shown

below) is not very good over a s igr i i f ica i i t 1-ange.

Taylor Form

T’he next form t o be g e n e r a l l y used was prcibably t h a t of Taylor.3 This

form i s u s u a l l y w r i t t e n

The parameters f o r many mate.ria1.s have been availab1.e f o r a long time

(mainly f rom ref. 3 ) .

aluminum, tungsten, and lead. and dose pa r ,me te r s f o r uranium have been

pub1.ished by S t r o b e l .

r a t h e r complete set of c o e f f i c i e n t s i nc lud ing values f o r ordinary,

ba ry te s , ferrophosphorous and magnetite coucrete . Pa,ramet,ers a r e given

f o r a11 p o i n t source r e s u l t s reported i n r e f . 1. The parameters f o r

t h e d.ose buil-dup i n concrete are based on data p b l - i s h e d by Walker and

Groterihuis. Since t h e d a t a are so complete, the dose, energy, and

energy abso rp t ion parameters a r e r e p r i n t e d i n this repor-1; (Tables 1-3).

These r e s u l t s are no t t h e same as those published p r e v i o i ~ s l y ~ ’ ~ but are

bel ieved t o be better because a more r e a l - i s t i c e f f e c t i v e atomic number

was assumed .

Addit ional energy ahsorpbion parameters f o r

4 Recent2.y Buscaglione srtd Manz-ini5 published a

6

Polynomial Form

Toe use of a 4-teYm polynomial, capable of good accuracy, became

gene ra l ly f e a s i b l e when CapoY published a r a t h e r complete set of co-

e f f i c i e n t s for many m a t e r i a l s i n 1958. That i s ,

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Coef f i c i en t s (6) f o r several. s e t s of energ ies a r e gi.ven as w e l l as co-

e f f i c i e n t s f o r a b i v a r i a n t f i t s o one may geiierate a s e t of f3 values Cor

any energy. I n f a c t , f o r t he comparisons descr ibed below, t h i s had i o be

done t o o b t a i n c o e f f i c i e n t s at t h e same energ ies used f o r t h e o the r para-

meter t a b u l a t i o n s . Unlike a l l o the r formula t ions considered here , Capo's

c o e f f i c i e n t s r e s u l t i n an express ion which does not reduce t o e x a c t l y one

f o r ~ L R = 0. The values of f3 a r e extremely c l o s e t o one, however. A s e t

of energy- absorp t ion parameters, where f3 = 1, f o r a l l m a t e r i a l s of even

A s e t o f dose para- atomic number up t o Z = 78 was piublished by Vondy.

meters f o r concre te based on d a t a f r o m rei". 6 has r e c e n t l y been published

by Buscaglione and Manzini.

0

10 0

1.1 This s e t i s reproduced i n Table IC.

8erger Form

A two-parameier formula proposed by Berger" and re in t roduced by

Chilton'' has t h e s i m p l i c i t y of t h e l i n e a r form but f i t s t h e bui ldup

f a c t o r d a t a we13 over a long range. This formula i s

I n r e f . 13, Chiitori gave t h e parameters f o r aluminum and shows t h a t Lhis

formula reproduces the bn-ildup f o r t h i s material . very- we1.I.

t o i n v e s t i g a t e t h e formula f o r oLhzr m a t e r i a l s and make it g e n e r a l l y

usefu.1, t h e au thor determined parameters by a l e a s t squ.ares procedure

f o r a l l the dose and energy- absorp t ion r e s u l t s gi.ven i n r e f . I. I n add.i-

Lion, dose values were determined f o r fou r types of concre tes based on

d a t a i n r e f . 6. Two s e t s of d a t a were obtained. One s e t i s based on

d a t a f o r pRr ; 7 and t h e o the r s e t i s based on data, f o r pR 2 G . These

values a r e gi.ven i n Tabl-es 5-8 f o r t he dose and energy absorpt ioi l buildul3

f a c t o r s . The maximum e r r o r encountered over t h e f i t t e d ranse i s given i n

t h e t a b l e s i n percentage o r as a f a c t o r ind-icated by t h e l e t t e r F . Shor t ly

af ter t h i s w a s doile, it was discovered t h a t ex tens ive d a t a were being

I n a.:n e f f o r t

2. :

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published by Rud1offl4 and by Chil ton. ’’ on data f o r pR I 1.5 and the Chi l ton values are based on d a t a for pR 5= 1.0

and so t h e parameters determined by the various authors are not t h e same.

Ch i l ton ’ s va lues are reproduced i n F igs . 1 and 2 as func t ions of energy f o r

var ious 1naterial.s. In Fig . 2 it can be seen tha- t f o r s eve ra l ma te r i a l s and

c e r t a i n energ ies t h e value of D i s zero which means t h a t t h e Uerger formul.a

reduces to t h e 1.inear f’orrn.

The Rudloff values are based

parameters f o r Lineal” and Quadratic Forms

In add i t ion to der iv ing t h e parameters f o r the Berger formula, t h e

parameters f o r t h e l i n e a r formula,

and the quadra t ic formula,

were determined by t h e author . Yne f i t t i n g procedure used for t h e l a t te r

two formulas minimized t h e resicl.ual~s r a t h e r tham the logarithm of the

r e s i d u a l s which resu1.ted i n a b e t t e r f i t f o r 1.s.rge values of‘ the argu-

ment r a t h e r than f o r small values . With heavy elements, t h e r e i s some-

t imes a l a rge e r r o r i n the f i t t i n g func t ion a t s m a l l d i s t ances such t h a t

t h e value of B, as deternined from Eq. 8 , goes t o ze ro o r i s negat ive.

This causes the absurd r e s u l t of a maximum e r r o r ra. t io of irifinri.ty! The

paiaameters for Eq. 7 ayld Eq. 8 a r e a l s o given i n Tables 5-8.

Other Forms

T’nere a r e many o the r poss ib l e buildup f a c t o r forms such as those

c i t e d by Ifuubbell but they a r e gene ra l ly more complicated than tine forms

c i t e d here. Hubbel l ’s power s e r i e s form, for- example, converges ade-

qi.iately a t s h o r t d i s t ances only and t2rxus u s u a l l y r equ i r e s many berms but

has t h e advantage of a separa t ion of t h e va r i ab le s dependent on medium

p rope r t i e s , geometry, and tn ickness .

16

Page 18: OF FWNCTIQ GAMMA-RAY BUILDUP F

- 6-

ORNL-DWG 65-44895

Fig. I . BERGER FACTOR C AS A FUNCTION OF ENERGY FOR VARIOUS VIATERIALS. (FROM REF 15)

2

0.5

C

0.2

0.1

0.05 0.2 0 . 5 4 2 5 10 20

PHOTON ENERGY (MeV)

Page 19: OF FWNCTIQ GAMMA-RAY BUILDUP F

-7-

0 .25

0.20

0.15

O.+O

D 0.05

0

-0 .05

- O , { O

-0.45

ORNL-DWG 65-iI896

Fig. 2. RERGER FACTOR D AS A FUNCTION OF' ENERGY FOR VARIOUS MATERIALS. (FROM REF 15)

.... ~

.~

...............

...............

............... 0.5 4 2

PHOTON ENERGY (MeV) 5 10 20

Page 20: OF FWNCTIQ GAMMA-RAY BUILDUP F

-8-

-I.- Graphical Comparison

Typi.ca1- graphs of t he var ious forms a r e given i n F igs . 3 - 38. Ex-

amples of some of t h e worst f i t s have been selec. ted t o r i l~ l~ i rs t ra te t h e prob-

lem a reas . Some o f -the b e t t e r f i t s are also shown t o i l lus-LraLe how good

many of the empir ica l func t ions a r e . Most of the parameters used f o r -the

l i n e a r , quadra t ic , and Berger formulas were taken from Tab3.e 7 . Most of

t h e Taylor parameters were taken from Table 1. However, most of t h e pol-y-

nomial parameters were generated. from t h e b i v a r i a n t c o e f f i c i e n t s of Capo

s ince val-ues f o r ,f3 a t t h e gene ra l ly used ene rg ie s a r e not given i n r e f . 9.

Most of t he i l l u s t r a t i o n s a r e f o r dose buildup f a c t o r s but, tlie o'cher types

behav-e sri.mi.larly. The Berger form i s given i.n every graph as a stand.a.rd

of comparison.

9

One of t h e most d i f f i c u l t ca ses i o f i t i s shown i n F ig . 3. This i s

t h e case of t'ne dose bui ldup a t 0.25 MeV i n water . It i s obvious t h a t t h e

1inea.r f 5 . t j s very poor over such a long range and t h e quadraLic f i t i s a l s o

very poor f o r dis tar ices less than 8 mean f r e e pa.tlis (mfp).

however i s reasonably good with a maximum e r r o r of about 50%.

parameters a r e not avai l -able below 0.5 MeV. i n F ig . 4 -the parameteys ax-e

based on d a t a f o r d i s t a n c e s l e s s than 7 mfp which r e s u l t s i n cons iderable

improvement, ecpecial-l-y in the quadra t i c f i t .

good polynomial fit , i s demonstrated. I n F ig . 7 it i s shown t h a t f o r 0.5

MeV t h e l i n e a r and quadra t i c f i t s a r e b e t t e r , p a r t i c u l a r l y tile quad.rat,ic.

I n Pig. 8 t h e Berger and 'Tayl-or f i t s a r e seen t o be nearly- identical^ and.

i n F ig . 9 the polyiiomial form i s aga in seen 'io be extremely good.

10 - 18 demons.Lratc that, a l l t h e f i t s a r e q u i t e good f o r l i g h t materials

a t t h e higher ene rg ie s .

The Berger f i t ,

Tayl_or

I n F igs . 5 and 6 the very

F i g i c e s

In F igs . 19 - 28 it can be seen t h a t t he l i n e a r and quadra t i c forms

work q u i t e we l l a t low energ ies i n heavy mater ia l -s bu t present d i f f i -

c u l t i e s a t 'the high ene rg ie s . F igures 29 - 30 show t h a t the si-Luation

improves when t h e r equ i r ed range i s decreased t o 7 mfp, wi-til Lhe quadra t i c

becoming q u i t e good.

F igures 31 - 36 show t y p i c a l r e s u l t s f o r ord inary concre-Le. Resu l t s

f o r t h e heavy concre.tes a r e simil-ar. The pol.ynomia1- c o e f f i c i e n t s were

taken from Table 4.

us ing tile parameters beyond tlie f i t t e d range of 7 mfp.

F igures 37 - 38 a r e included t o show t h e danger of

Page 21: OF FWNCTIQ GAMMA-RAY BUILDUP F

. - -9-

S t a t i s t i c a l . Comparison of 'I'ayl.or and Berger Forms and Conclusions - It appeared f rom g raph ica l cornprtri.sons tha t t h e 2-parameter Herrger f orin

was o f compa.rab1.e accuracy t o the 3 -parameter Tayl.or form. I n order t o

eram?.ne I ;h t2 two forms fur12ter , t h e a.vei-age devtation was computed f o r

var ious materia3.s. 'The average devia,tio:n wa,s taken - to be

where

rJ =

B J E ~ , R , ~ ) =

R 13(EiyR.) =

J

riiiniber of ene rg ie s =r- 8,

niunber of clistanees = 7 (usual.l.y),

t ahu l~a ted bui ldup factor ( r e f . 1 o r 6), value given by a, formula.

-,_ .t 2

This t e s t was performed. by Chi l ton for c e r t a i n cases with t h e r e su l t

that the Rerger -for~iirln was found. supe r io r .

c a t e the ttcci.zra,cy i s about the same. This leads 11s t o recotnmend t'ne Berger

fcrrmila except where t h e very b e s t f i t i s d e s i r e d i n which case t h e

polynomial form i s recorritiierided. Actual ly , as Chiltoil l ' poirl ts olut,

of t h e b e t t e r forms y i e l d r e s u l t s wi th in t h e u n c e r t a i n t y of 'Lhe basic

d a t a which i s g t v e n as 5-lC4.

ovei. the Taylor form which are:

0u.r r e s u l t s (Table 9) i n d i -

1 The Berger fornl11l.a has s e v e r a l advantages

1. I n the Bergel. f o r m t h e two terms a r e p h y s i c a l l y rneaning-€u.l.

The f i r s t t e r m r e p r e s e n t s the uncol l ided flux and t h e second

term r e p r e s e n t s -the s c a t t e ~ e d f l u x .

2. The parameters are more s l . 0 w l y varying b . i - j _ t h energy, e s p e c i a l l y

i n the case of water at low ene rg ie s . As can be seen i.n Table

l,the Taylor parameter A changes by a f a c t o r o f 5 between 1

and 0.5 MeV whi.1.e t h e Berger parameter C cbafiges by only a.boiit

4@. The Taylor form i s easi.1.y f i t t e d into t h e framework of the i incol l ided

tI.ux equat ions, bu-t t h i s i s no-t a g r e a t advantage s i n c e 'Lh? Bereer Yorrt! i s

easy Lo i n t e g r a t e , which is i l l - u s t r a t e d below.

Page 22: OF FWNCTIQ GAMMA-RAY BUILDUP F

1 o3

1 o2

C E 0 t- o B

L 3 e3 -I

3

10'

+-I

m

1 oc

10-

- 10-

ORNL-DWG 65-41897

Fig. 3. ISOTROPIC SOURCE IN WRTER KlOSEs .25 MEVs 20 MFPl

DISTRNCE FHQM SClURCE [MFPB

Page 23: OF FWNCTIQ GAMMA-RAY BUILDUP F

- 11-

ORNL-DWG 65-11898

(r D t- o a L L

a. 3 Q -I 3 M

I-+

Fig. 4. ISOTROPIC SOURCE I N WFITER (DOSE9 25 MEV9 7 MFPI

X QUADRATIC + L INEAR

BERGER 0 REF4

3 F 0 I 0

O I S T R N C E FROM SOURCE [MFPI

Page 24: OF FWNCTIQ GAMMA-RAY BUILDUP F

-12-

Fig. 5. ORNL-DWG 65 -11899

3 f

* POLYNOMIAL - 2 BERGER

0 REF4

I 8.0 10

OISTRNCE FAOF SOURCE LMFPl

Page 25: OF FWNCTIQ GAMMA-RAY BUILDUP F

-l3-

1 o2

ORNL-DWG 65-11900 Fig. 6.

ISOTROPIC SUURCE IN WRTER KIOSEs a 25 MEVs 7 MFP)

."I- O REF4

- 3 I

7

r------ 6,

DISTFlNCE FROM SOURCE [MFPI

Page 26: OF FWNCTIQ GAMMA-RAY BUILDUP F

- 14.-

9ISTRNCE FROM SOURCE I

Page 27: OF FWNCTIQ GAMMA-RAY BUILDUP F

-15-

OkNL- DWG 65- 1’1902

Fig. 8. ISOTROPIC SOURCE IN MFlTEA (DI1SEs g S MEV9 20 MFP)

f

3 6

0 REF4

-

3 8.0 T 12

7

DISTRNCE FPUM SOURCE LMFPl

Page 28: OF FWNCTIQ GAMMA-RAY BUILDUP F

-

Fig. 9.

16 -

ORNL-DWG 65-44903

Page 29: OF FWNCTIQ GAMMA-RAY BUILDUP F

- 1.7-

ORNL-DWG 65-1 1904

Fig. 10. ISOTROPIC SOURCE I N WRTER KIOSE) 2 MEVs 20 MFP)

3

DISTRNCE FROM SOURCE (MFP)

Page 30: OF FWNCTIQ GAMMA-RAY BUILDUP F

- 18-

ORNL-DWG 65-11905

Fig. 1 I .

1 o2

I

[r D t- o a lL 10' a 3 c1 J

3 H

m

!

ISOTROPIC SOURCE I N WRTER (013SEI 2 MEVY 20 MFPl

0 TAYLOR Z BERGER 0 REF4

/ /

3 DISTRNCE FROM SOURCE (MFPI

Page 31: OF FWNCTIQ GAMMA-RAY BUILDUP F

- 1-9 -

OR N L- DWG 65 - i 4 906 Fig. 12.

I S O T R l l P I C SOURCE I N WRTER (DOSE1 2 MEV9 20 MFPl 1 o2

a D t- o cz:

a. 3 0 J

3 M

LL 10'

H

1 OD

/

3

* POLYNOMIAL Z BERGER 0 REF4

t I 10 I

DISTRNCE FROM SOURCE (MFPI

Page 32: OF FWNCTIQ GAMMA-RAY BUILDUP F

-20-

ORNL-DWG 65-ii907 Fig. 13.

TROPIC SOURCE IN WATER [%NEB, RBSm 9 6 FIEUP 20 MFP)

P

X

+ z 0

---

QUAD R ATK LINEAR BERGER REF 1

3

DISYRNCE FROM SOURCE [N%$I

Page 33: OF FWNCTIQ GAMMA-RAY BUILDUP F

-21-

ORNL-DWG 65-41908 Fig. 14.

ISOTROPIC SOURCE I N WRTER KNER, RBSm9 6 MEV9 20 MFP) 1c' -

/ rAY LO R BERGER

Page 34: OF FWNCTIQ GAMMA-RAY BUILDUP F

-22-

ORN L- DWG 65- 14909

/

_I_

0

'OLYb ip. BERGER 0 REF4

I_r_.

MlAL

I

- 6

Page 35: OF FWNCTIQ GAMMA-RAY BUILDUP F

. I

- 2.3 -

OR N L- D'NG 65 - ! 4 9 10 Fig. 16.

........ .......................... ....... .- ... - __

Page 36: OF FWNCTIQ GAMMA-RAY BUILDUP F

-24-

ORNL-DWG 65-119'11

fig^ 17.

I Q0

0 TAYLOR Z BERGER 0 REF!

Page 37: OF FWNCTIQ GAMMA-RAY BUILDUP F

-25-

ORNL-DWG 65-4i912

Fig. 18.

1 o2

a 0 I- u a

n 3

LL 10'

9 H 3 al

1 O0

ISOTROPIC SOURCE IN RLUMINUM EXlSEo 6 MEYo 20 MFP

POLY N OM I A L BERGER REF 1

10

/

!

p""c

I

DISTRNCE FRUM SOURCE [MFPI

Page 38: OF FWNCTIQ GAMMA-RAY BUILDUP F

-26-

10'

1 OD

E- l

u k- 0 U- LL.

L 3

J

3 co

n c1

10"

t

1 o-2

OR N L- DWG 65 - 4 i 9i 3

Fig. 19. IS(JIf3UPiC SOURCE IN LEQU (DOSE9 0,s MEV9 20 MFP)

e --,/

....

...............

JUADFi

.._.............

ss+- _*-- .--- ................

.....

................ ....

...................

a. a 10 1

...............

... __

OISTRNCE FROM SOURCE [MFPI

Page 39: OF FWNCTIQ GAMMA-RAY BUILDUP F

-27-

.

ORNL-DWG 65-11914 Fig. 20.

IN LERD (DOSE7 3 MEUY 20 MFPI

QUA 0 RAT I C

LINEAR EERGER REF 4

0 10 12 I

OISTRNCE FROM SOURCE [MFPI

Page 40: OF FWNCTIQ GAMMA-RAY BUILDUP F

-28-

ORNL-DWG 65-(1945

Fig. 21. ISOTROPIC SOURCE I N LE9D IDOSE9 3 MEVY 20 MFPl

0 TAYLOR Z BERGER 0 REF4

f 3 I 3 I

- .........

7"

........ 3 i 3

_ ........ ..

OISTFINCE FROM SOURCE LMFPl

Page 41: OF FWNCTIQ GAMMA-RAY BUILDUP F

-29-

ORNL-DWG 65-11916

Fig. 22.

ISOTRUP IC SOURCE IN LERD (DOSE9 3 MEVs 20 MFPl 1 o2

a r) r- 0 CL

a 3 cl J

3

LL 10'

l--i

m

POLYF lMlAL * 2 BERGER

REF 1

7'

f

0 ' I 0 O

DISTRNCE FROM SOUACE LNFPl

Page 42: OF FWNCTIQ GAMMA-RAY BUILDUP F

-30-

Fig. 23. ORNL-DWG 65-ii917

ISOTROPIC SOURCE IN LEAD IDOSE? 6 MEV? 20 MFPI

3 E

Q cl A 0 R AT-l C

1.1 NEAR SERGER -

REF 4

................._

12

_I-

/ /-

I

OISTRNCE FROM SOURCE LMFPl

Page 43: OF FWNCTIQ GAMMA-RAY BUILDUP F

-31.-

Fig. 24. 0 R N L- D WG 65 - 4 i 9 4 8

10'

Llc c3 E- u a LL 1Q' a_ 3 a -I

3 - m

1 oo

ISOTROPIC SOURCE IN LERD (DOSE9 6 MEV9 20 MIFF')

6 TAYLOR BERGER

Q REF4

J

f

OISTRNCE FRQN SOURCE LMFPl

Page 44: OF FWNCTIQ GAMMA-RAY BUILDUP F

-32-

OHNL-DWG 65-11949

Fig. 25. ISOTROPIC SOURCE I N LEAD (DOSE9 6 MEVs 20 MFPI

.

/ 0 4

PO LY N 0 M I A L BERGER REF 1

o i 0 D

--

.....

4

Page 45: OF FWNCTIQ GAMMA-RAY BUILDUP F

-33-

.

ORNL-DWG 65-41920

Fig. 26. ISOTROPIC SOURCE IN LERD I D ~ S E P 10 MEV? 20 MFPl

1 3

X

+ z 0

-

OISTRNCE FRQN SOURCE CNFPl

Page 46: OF FWNCTIQ GAMMA-RAY BUILDUP F

-34-

Fig. 27. ORNL-DWG 65-1192(

1 o2

I

[r D I- u a

10' a_ 3 0 II

3 w

m

C

'

l o o ,

ISOTROPIC SOURCE IN LEAD (DOSE, 10 MEV, 20 MFP)

2

0 z 0

TAY LO w BERG E R REF 1

--

I

Y f

DISTRNCE FROM SUURCE LMFPl

Page 47: OF FWNCTIQ GAMMA-RAY BUILDUP F

-35-

Fig. 28. ORNL-DWG 65-14922

894 2

ISOTROPIC SOURCE I N LERO IDOSE9 10 MEV9 20 MFPl

/ 3 '

POLY N 0 M I A L BERGER REF i

B

3

L

k

DISTRNCE FROM SOURCE LMFPI

Page 48: OF FWNCTIQ GAMMA-RAY BUILDUP F

-36-

ORNL-DWG 65-11923

Fig. 29. ISOTROPIC SOURCE IN LERD KIOSE9 6 MEV9 7 MFPl

a

X QUADRATIC

f LINEAR BERGER

0 REF4

0 0

a I STRNCE FROM SOURCE LMFPI

Page 49: OF FWNCTIQ GAMMA-RAY BUILDUP F

. -37-

Fig. 30. ORNL- DWG 65-11924

ISOTROPIC SUURCE I N LEAD (DOSE9 10 MEVs 7 MFPl

4

1 3

X QU DRATIC - + LINEAR

Z BERGER 0 REF4

3 3.0 3 I

OISTRNCE FROM SOURCE [MFPI

Page 50: OF FWNCTIQ GAMMA-RAY BUILDUP F

-38-

ORNL-DWG 65-il925

Fig. 31. ISBTROPIC SOURCE I N OHU, CONCRETE (D~%J 1 MEVl

5@ "-'

/ @ ~ .......

f ..... P '1

QUAD1 1-1- I c X

+ 2

0

LINEAR BERGER REF 6

.

........ .......... .-

-- 0 8.0 l o

..

...

____

.......... _- 0

DISTRNCE FROM SOURCE IMFPI

Page 51: OF FWNCTIQ GAMMA-RAY BUILDUP F

. *

. -39-

1 o2

!x I- o U

Q 3

IJ 3

LL lo1

a

m H

c

d

I O 0 \

ORNL- DWG 65- 44926 Fig. 32.

I S O T R O P I C S O U R C E IN ORD, CONCRETE IDOSE4 1 MEW

DISTRNCE FROM SOURCE (MFPI

Page 52: OF FWNCTIQ GAMMA-RAY BUILDUP F

ORNL-DWG 65-1i927

1 o2

E

ar 13) +- 0 CL

a. 3

10' n

m H

3

1 oa

Fig. 33

ISOTROPIC SOURCE I N ORD. CONCRETE (DOSE9 1 MEVl

.. ... ._. / x z 0

3 3

DISTGNCE FROM SOURCE lMFPl

Page 53: OF FWNCTIQ GAMMA-RAY BUILDUP F

L

-4.1-

ORNL-DWG 65-11928

1 o1

a f, t- o ct

a. 3 0 J 3 c13

loo

H

10-

Fig. 34. ISOTRClPIC SOURCE I N QRD, CQNCRETE (DOSE9 6 MEW

LINEAR BERGER

0 R E F 6

\TIC

OISTRNCE FROM SOURCE (MFPI

Page 54: OF FWNCTIQ GAMMA-RAY BUILDUP F

-42-

F-ig. 35 OHNL- DWG 65-11929

ISaTROPIC SOURCE IN URD, CONCRETE (DOSE9 G MEW

.............. I 1 I F

0 A Y L O R Z BERGER 0 R E F 6

...............

/ -.. ...........

..............

DISTRNCE FROM SUUHCE (MFPI

Page 55: OF FWNCTIQ GAMMA-RAY BUILDUP F

-43-

Fig. 36 ORNL- DWG 65-1 1930

ISOTROPIC SOURCE I N URD, CONCRETE (DOSES 6 MEV)

1

I

k B

* Z

0

I I

’OLY NO M I A L 3ERGER REF 6

I

p”’

--

DISTRNCE FROM SOURCE IMFP)

Page 56: OF FWNCTIQ GAMMA-RAY BUILDUP F

-44-

OHNL-DWG 65-ii931 Fig. 3'1.

ISOTROPIC SOURCE IN LERD (DOSE9 6 MEVY 7

. . .. . A a I. I c

X

3-

Z

0

O E

QlJ A D RAT1 C

LINEAR - BERGER REF 1

k 0 10

MFPI

Page 57: OF FWNCTIQ GAMMA-RAY BUILDUP F

-45-

10'

a

a

B I- u

LL loo a. 3 Q J

3 c-(

m

lo-'

ORNL-DWG 65-11932 Fig. 38.

I so

k

2

DISTRNCE FROM SOURCE [MFPI

Page 58: OF FWNCTIQ GAMMA-RAY BUILDUP F

-46-

Table 1. Buscagli.one-Manzini* Coe€f ic ien ts for Tayl o r Dose Bii ldup Fac tor Formula

- - Max imiim

A -4 Percent

Deviat ion

Water 0.5

1

2

3

4

6

a 10

Aluminum 0.5

1-

2

3 4

6

8 10

Barytes 0.5 Conc ret e

1-

2

3 4 6

8. IO

100.845

19.601

12.612

11.110

11.163

8 0385 4.635

3 543

38.911

28.782

16.981

ic.582

7.526

5.713 4.716

3 999

33.026

23.014

9.350 6.269

4 d 130

2.167

1.433

3.240

0.12687

0.09037

0.05320

0.03550

c .025[~3

0.01820

0.02633

0.02991

0 . 1 0 ~ 1 5

0.06820

0.04588 o.oJl066

0.03973

0.0593 4

0 03837

0.03900

0.06129

0.06255

c. 0606h

c. 0650c

c .080oc

0 .0951J+

0.3 1.201

0.05700

- 0.10925 - 0.02522

0.03206

0.03 025

0.041 64

0.07097 0.08(17

- 0.06312

0.00271

0.03860

0 .0443 1

0.01932

- 0.02973

0.02514

0.04347

C. 04130

- 0.023a3

- c.02217

0.03850

0.0Llc40

0.05883

0.061107

0.07857

0.13c21

- 29.4 px = 10

- 10.8 px = 10

-t. 4 . 2 p x = 1

-1. 1.7 px = 1

-t 0.8 px = 20

- 0.5 p,x :I: 2

-1- 0.6 px := 7

- 0.7 px = 1

- 12.2 px == 10

.- 8.6 p , ~ := 1.0

- 5.2 p,x = 10

- 2.5 px = 10

+ 1.8 px = 20

3- 1..6 px = 20

- 1.3 px = 1 5

+ 1..2 j.lx = 20

+ 7.5 px := 2

4.- 8.9 px = 20

+ 9-0 px 'I= 2

.i- l+ .8 PX = 20

+ I+.8 IJ,X = 2

+ 5.0 IJ.X = 2

+ 1.3 px = 20

-t- 3.2 WX = 2c

*Taken fyom Ref. 5.

Page 59: OF FWNCTIQ GAMMA-RAY BUILDUP F

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l'ab1.e 1 (continued)

Msxirnum Percent,

- 4 (3 Devis Lion Material & (MeV) A

1

2

phorous Concrete

46.087 0.05202 - 0.02845 + 10.3 p~ = 2

14.790 0.04720 0.00867 -t 3.0 g~ =: 2

3 i0.309 0.04290 O.O?211 + 2.6 px = 20

4 6.240 O.O>FBO 0.03765 -t 1.7 ~ J . X = 2

6 4.425 0.05880 0.04262 - 1.0 px = 2

8 3.900 0.06750 0.05730 + 0.8 1-1" = 4

10 2-279 0.07575 0.06438 t 0.4 px = 6

Oydinary 0.5%

i

2

3

4

6

8

10

Cone re te 38.225

25 507 18.089

13.640 11.lc60

io. 781. 8.9 '2

4.015

0. i4824

0.07230

0.04250

0.03200

0.02600

0.01520

0.01300

0.02880

- 0.10579

- 0.01811-3 0.00849

0.02022

o.o2!i-50

0.02925

0.02979

0.06844

- 7.5 px = 4

-I- 11.1 px = 2

t '+*'3 px = 2

.t 4.3 px = 2

- 5.1 px = 2

- 2.7 px = 2

- 3.7 vx = 2

- 2.2 px = 2

Magnetite 0.5 75.".71 0.07479 - 0.05534 + 15.9 PX = 2

1 49.916 0.05195 - 0.02796 t 11.5 PX = 2

2 14.260 0.04692 0.01531 + ]+.O p~ = 2

3 8.160 0.0470O 0.011590 i- 5.0 p . ~ = 2

Concrete

J+ 5.580 0.05200 0.05728 -t 2.7 p~ = 2

G 3 . '137 0.06000 0.11520 + 4.3 p~ = L

8 2.480 0.06645 0.14002 t 4.0 p~ = PO

10 1.7 )+3 0.08~82 0.27209 -I- 5.3 px = 20

*For some materials, t'ne vaJues of the buildup fac tor for give11 energies a re known on1.y in the i n t e r v a l of 1 I px 15. I n these cases, designated by an as ter isk, the parameters are v a l i d up t o px = 15.

Page 60: OF FWNCTIQ GAMMA-RAY BUILDUP F

-48-

Table 1 (continued)

Maxi.rnurn Percent

Material. E, (MeV) A -04 a;! D evi.at i on

I r o n 0.5 1

2

3 4 6 8 10

0.5"

Tin

i

2

3 4 6 8 10

0.5*

1

2

3 4

6 8 10

31 -3 19 ?'+ * 957 I I .622

9.624 5.867

3 0243 1.747

1.677

13.218

2.984 5.421 5.580

0.926

0.368 0.311

3 -897

11.440 I:. jc26

8.783 5. lcoo

3.495 2. 005

1.101

0.708

0.06842 0.06086 0.0462 0 . c 4J 13 1 0.011698 0.06150 0 .07 5 00 0.09900

C .03 084 0.05503

0.03482 C. 05422 0.08468 0.17860 0.23691 0.2402Jt

0.01820 0.04266 0.05349 0.07440

0.09Sll 0 1-3733 0.17288 0.19200

- 0.03742 - 0.02463 - 0.00526 - 0.00087

- 0.001-86 0.02123

0.06627

0.00175

0 -30943- 0.131~86

0.04379 0.00611

- 0.04635

- 0.02783

0.03187 0.01606

0.02080 0.02598

- 0.01501. - 0.01787

- 0.02383

- 0.05684

0.01505

C. 01552

- 6.5 ~ J . X = 10

- 6.4 px = 10

+ 4.0 !J.X = 2

.I 3.0 PX = 10

- 2.7 px = 10

3 2.1 px = 20

+ 3.8 wx = 4 + 3.7 px = 2

- 0.8 px = 10

- 1 .0 l&X = 1

- 0.6 px = 1

+ 1.3 px = !+

4- 1.3 px = 20

- 0.5 px = 1

.- 1.6 P X = 1

- 2.8 px = 10

-I- '1.3 px = 20

- 3.9 px = 10

- 2.8 p , ~ = 10

- 3.4 px = 15

-t 1.4 wx = 20

+ 1 .8 LLX = 15

- 2.6 PX = 10

+ 2.6 P X = 15

Page 61: OF FWNCTIQ GAMMA-RAY BUILDUP F

I 14.9-

Tab1.e 1 (continued)

Material P -a (MeV) A Percent .c5 % De r i i a, t i on

'Tung st en 0.5*

1*

2*

4

4

6

8

10

UI-~JJ i.im 0.5*

1%

2*

3 4

6

8

1.0

2 ~ 6 5 5

3 2 3 4

3 504 4.722

5.520

0. 664 0.509

1.273

I I444

2.081

3.287

4.883

2.800

0.975 0.602

0.399

0.0Sg40

0.047 54

0.06053

0.08857

0. s7257

0.20710

0.06468

0.21743

0.021~59

0.03862 0.03997

0.04950 0.08240

0.15886

0.213111-

0.131.89

0.1.1-340 0.13058 0.08862 0.01404

- 0.04570

- 0.1.21-78

0.05025

0.04692

0.35167 0.2263 9 0.08635 0.00981

0.00370

0.21101

0.0qp.1

0.02083

- 4.9 px = 2

- 0.9 p'x = 10

+ 2.1L p'x = 10

- 2.4 px = 1.0

+ 1.3 px = 20

- 2.9 px = s3 + J..4 1.1" = 10

- 3.6 l&x = 15

- 0.9 px = 10

- 0.7 px = 10

- 0.5 px =

- 0.9 px = 15

- 2.2 PX = 15 - 2-1. c L ~ = 15

- 2.9 p~ = 15

1

+ 1.4 p , ~ = 4

Page 62: OF FWNCTIQ GAMMA-RAY BUILDUP F

-50-

Table 2. Ruscaglione-Manzi.ni* Coefficients f o r Taylor Energy Buildup Factor Formula

A -4

Maximum Percent

Deviat ion

Water 0.5 1

2

3

4 6

8

10

Alu.minum 0.5 1

2

3

4

6

8

10

I ron 0.5

I.

2

5 4

6 8 1.0

59.611.

27.060

17 430

11.954

i o . 661.

7-1-71 4 * 1-55

3 - 509

42 e 081

42 -116 5

26.516

15.260

5.776 1+.34'7

8.308

3 .TO4

36. '+79

16.610

12 ,481

9.929

4.893 3.209

2.981

24 a 481

0.12428

0.07840

0.04200

0 02907

0.02222

0.01902

0.025 5 1.

0 02590

0.10038

0.06329 0.03591

0 02925

0 03193

0.03337 0.03 483

0.03592

0.06602 0.06061

0.04527

0.04205

0.0427O

0.05'313

0. 06900

0.07040

- 0.094-66

0.00288

0.02267

0.02525

0.036'7 7

0.05620

0.06816

- 0.03349

- 0.06388 - 0.03789

0.00785

- 0.00877

0.02497

0.0512 I

0.03632

0.03448

- 0.03800

- 0.00728

- 0.00236

- 0.00256

- 0.00100

- 0.00124

- 0.02470

- 0.01575

- 22.6 p , ~ = 10

- 9.8 p x = 10

-t 3.6 p , ~ = 1

- 1.3 L L ~ .:= 10

- 0.9 p~ = 15

- 4.9 px ::- 1-5 - 2.4 px = 1.0

- 0.4 px = 2

- 12.7 px = 10

- 8.2 p~ = 10

- J+.5 LLX = 10

3. 2.2 px ::: 1

-t 1.3 I - L ~ = 2

4- 1.1 px == 20

- 1.1 px :: 15

3. 1.0 px = 20

- 6.3 \LX == i o - 6.6 px = 1.0

- 4.3 px ::: 10

- 3.0 px = 2

-t 2.3 px = 20

- 1.7 px := 10

-t 1.8 VX = 20

- 4.9 px = 15

*Taken f r o m Ref. 5.

Page 63: OF FWNCTIQ GAMMA-RAY BUILDUP F

- 51-

abl le 2 (cont inued)

M a t e r i a1 Eo (MeV) A -04 Maximum Pew c e nt D evia ti on

Le ad , 0.5"

1

2

3 h

G

8

1.0

Tin 0.5*

1

2

3 4 6 8

10

Tungsten 0.5*

l*

2*

3 4 6 8 10

2.025

3 468 4.709 4.804 3.729 0.842

0.421+

0.267.

11.480 21.1.14

21.7 11 6 11.330

3 960 4.413 0 897 0. $30

1.877

5.986 4 * J+oo 2.200

0.93l 0.561 0.386

4 rn 120

0 01.330 0.02163

0.03641. 0.04pg

0.08084 0.17000

0.23 120

0.21074

0.01840

o .03 08'7

0.03512

0.05340 0.08299

0.11.038

0.16669

0.18746

0 03373 0.03403

0.03776

0.06240

0.10700

o .1i 0)+4 0.19800 0.21250

0.19040

0. logoo 0.04723

0.00722

- 0.02992 0.05092

- 0.01158 - 0.01945 0.03032

- 0.00142 - 0.01200 - 0.020b-7

- 0.00222 - 0.08253.

+ 0.01782 - 0.00962 0.26061 0 .087 57

0.01135

0.01520

0.03098

0.14967 0.02843

0.01112

+ 5.9 px = 15

- 2.3 px = 10

+ 0.6 px = 2

- 1.2 px = 1.5

t- 0.9 p~ := 20

- 0.5 p~ = 15 + 0.6 px = io

+ 1.1 px = 10

- 2.2 px = 1

- 2.2 p x = 3.0

- 2.0 px = 10

-!- 2.7 px = 4 - 2.6 px = -

- 1.)+ px = 15 10

- 2.6 p~ = 15 - 2.8 px = 1-5

- 0.6 p~ = 10

- 1.1 px = 1

- 0.5 px = 1

-t 1.7 px = 20

+ 2.6 px = 2

- 2.4 px = 1.5

+ 1.3 PX := io

- 3.2 p~ =: 1-5

*For some materi.als, the values of the buildup f a c t o r for given energies are known only i n the i n . t e r v a 1 of 1. 5 px < 15. I n these cases, desig- nated by an asterisk, Lhe parameters are valid up t,o px 2 15.

Page 64: OF FWNCTIQ GAMMA-RAY BUILDUP F

- 52-

Table 2 ( c o n t i n u e d )

Ma i; e i' i a 1 (MeV) A az Max irnutri Percent

Deviation

Uranium 0.5" 1*

2*

3 4 6 8 10

1.492 2.052

2.600 4.000

2.166 0.F59

0.593

0.378

0.02146 0.0381lc 0.0)-~760 0.05110

0.08506 0.115319

0.17773 0.1.9727

0.30891 0.22109 0.10850

0.01453 0.01540

0.03'7 97

0.08500 0.02658

- 0.7 px = 10

- 0.9 px = 1

- 1.8 px = 10

c 1.1 px = 20

- 1.2 PX = 15 - 1.3 W-LX = 15

- 2.> px = 2

-t 2.7 p~ = io

Page 65: OF FWNCTIQ GAMMA-RAY BUILDUP F

-53-

Table 3. Biscaglione-Manzini* Coefficients for Tayl-or Ene rgy Absorption Bui1.ci.up Factor- Formula

Maxiuium

A -% Percent

Deviation

I r o n

I R ad

Water 0.5 40.006 0.13587 - 0.09220 - 24.1 PX = 10 1 34.832 0.08000 - 0.01~377 - 12.2 p~ = 10 2 23.002 0.0~-1050 - 0.00080 - 4.8 p~ = i o 3 16.326 0.02’728 0.02080 f 1.5 P X = 1 11 11.330 0.02527 0.0302’7 , + 1.0 p~ = 20 6 6.280 0.02610 0.05658 + 0.6 c L ~ = 2 8 J-c.314 0.02914 0.0’7839 - 0.7 \LX = 15 1.0 3 . G l O 0.02’7 90 0.07990 - 0.7 px = 15

Aluminum 0.5 74.220 0.09g40 - O.0764O - 13.5 ILX = 10

2 34.530 0.0g599 - 0.01068 + 5.5 pic: = 1 1 52.022 0.06395 - 0.04023 - 8.8 LLX = 7

3 28.581. 0.02343 0.00073 + 2.2 I . L ~ = 1 4 25.364 0. 01800 0.00361 + 1.4 PX -- 20 6 19 . ’ ~ ’ ( ’ 7 0.01.543 0.00516 - 0.9 l L ~ = 15 8 17.528 0.01421 0.00566 - 0.9 c L ~ = 15 10 12.4 07 0.01.695 0.00351. - 0.8 pX = 15 0.5 39.556 0.07500 - 0.02957 - 7.1 px = 10 1 27.215 0.06496 - 0.01828 f 6.5 PX = 1

3 13 0398 0.04425 0.000g2 - 2.9 px = 10 4 9.261 0.04952 0.00027 - 2.0 p~ = i o 6 5.052 0.06040 0.001.35 + 2.0 LLx = 20 8 3.875 0.06504 - 0.01237 - 1.4 p~ = 10 1.0 3.101 0.07561 - 0.03sgg -t 1.0 p~ = 1

2 6.502 0.0371~6 0.05631-r - 2.0 p~ = 1 3 7 -194 0.04800 0.00000 - 1.2 px = 1 4 2 - 529 0.09087 0.00000 - 1.2 px = 1.5 6 0.772 0.16600 0.03822 - 0.8 px = 1

0.5 8.405 0.05137 0.11076 -- 1.4- p~ = 1~5 2.0 < px = 15 1 18.518 0 03995 0.02017

3 18.534 0.04851 - 0.02219 - 9.2 p , ~ = 1.5

2 1-9.705 0.04569 - 0.00509 - 4.0 px = 10

0.5** 2.030 0 0373 9 0.5064-4 - 2.2 p , ~ = 1: 1. 4.1.92 0.04258 0.18642 - 2.0 p , ~ =

8 0.381. 0.20345 0.00000 - 1.6 p~ = 2 10 0.171 0.23500 - 0.03151 - 0.7 IJ.X = 1

- 2 14.587 0.04.623 0.00774 - 3.9 p , ~ zz 10

4- 11.519 0.06551 - 0.03733 - 8.4 px = 1.5 6 1.457 0.12900 - O.OlO58 - 2-2 vx = 7 8 0.811.1 0.16056 0.00000 - 2.0 px = 1.5

10 0.63‘7 0.17284 0.04635 - 1.3 w~ = 15 ..-...-.~-I_cI-----.- -... ^- ” , ._,.__ _,. ~

-gTaken from R e f . 5. *$’or some materj-als, -the va!.ues of t h e bui ldup f a c t o r for given ene rg ie s are known only i n tine i n t e r v a l of 3. p,x 5 1-5. I n these cases, desi.g.mted b y an asterisk, the parameters are v a l i d up - to px = 1.5.

Tin

Page 66: OF FWNCTIQ GAMMA-RAY BUILDUP F

Table 4. Buscag!.ione-Mamini* Polynomial Coef f i c i cn t s for t h e Dose Buildup Fac to r i n Various Coiicre’ces

E Mev Bo GI. P3 I33 * m a % A 4

Ordi-nary concrete

1 5.1902(-1) 1.6152( 0 ) 2 7.7342(-1) 9.1835(-1) 3 1.0530( 0) 6*3743(-1) )+ 1.1506( 0 ) 4.9800(-1) 5 1.1806( 0) 4=1634(-1) 6 1.1846( 0) 3.6314(-1) 7 l.l781+( 0 ) 3.2590(-1)

Magne ii.te concrete

I 5.2780(-1) 1.1562 2 9.3721(-1) 8.0638 3 9.5856(-1) 6 . y i - 3 4 9*7216(-1) 5.3998 5 9.8690(-1) 4.5747 6 1.0010( 0) 3.9452 ‘7 1.@237( 0 ) 3.4521

5.4702 (-2 )

1.6185 (-2)

7 2 3 7 6 ( - 3 )

3 .GO51 (-1)

2.7260(-2)

1.0547(-2)

5.0942 ( -3 1

9 - 7 936 ( - 2 ) 3.1686(-2) 1.3680( -2)

5.8668 (-3 ) 5.2611(.-3)

7.8749c-3 1

5 02272 (-3 )

6.6197 ( - 2 ) 2 .4051( -2) 1.3122(-2) 8.272-7 (-3 ) 5 5458(-3) 3-7988(-3) 2.5837 (-3 1

1.3686 (-1) 3.5826 (-2 ) 2.01O6(-2)

7.2573 (-3 1 I. 3442 (-2 )

6.2307 ( -$ ) 3 *897’1(-3)

1.8803(-3)

-3.8875(-4) -2.9613(-4) -2.2268(-!1) - 1.6888 ( - 4 ) - 1. 2895 (- j+ )

-3.9911(-4)

- 1.4084 (-3 ) - 4.95 03 ( - 1-L ) -2.0725(-4) -1.0316 (-4)

-Lt 1859( -5 ) -3.4147 ( - 5 )

-5 - 037 5 (- 5 1

- 2 . 6 9 ~ 9 ( -l+ )

- 2.8460 ( - 5 ) 8.221.0 (- 5 ) 1.7 1+78 (- 4 ) 2.4954(-1-1-) 3.1005(-1+)

- 1.3’1 47 ( - 4 )

-2.7616(-3) -5.2672(-4) -2.9295(-4-) -5.0691 ( - 5 ) 1. 8O)cJ;- ( - 4 ) 3.8250(-4) 5 .5449( - J-I )

-3.6 p,X=lt* 1.2 px=2

-3.9 px=2 -1.9 px=8 2.8 px=2 2. I J L X : : - ~

-1.3 px=4

1.8 px=20 1.5 PX= 8 -1*6 px= I+ -2*3 px=io 1.8 L x = ~ o

2.6 l L ~ : = 8 3 .O IJ,x:=J.C

2.1 }LX= 4 2.2 vx= 8

-5.4 px= 6 -3 .a px::.14 2.11 px= 8 5 -3 LLX= 8 4.0 WX= 8

1.8 0.4 1.2 0.8 1.3 0.9 0.4

0.8 0.6 0.6 1- .7 1 .0 2.3 1 . h

0.7 0.5 1.1 1.5 1.0 2.4 1 .6

1.0 1.1 2.6 2.2 1. . 5 3 -8 2.9

-WIiis value of px i s t h e value for which t h i s error i s va l id .

*Taken from Ref. 11.

Page 67: OF FWNCTIQ GAMMA-RAY BUILDUP F

- 5 5 -

Table 5. Linear , Quadra.l;ic and Berger Coefficients f o r Dose Buildup Formid-as F i t t e d over t h e Range

(0-7 b"P)

Page 68: OF FWNCTIQ GAMMA-RAY BUILDUP F

-56-

( c o n t . ) WATER DOSE BUILDUP

POINT ISOTROPIC SOURCE 7 W P F I T

M A X I MUM A 1 E R R 0

8,6524 Fa. I

4,6800 F2*3

1,8953 &a% 1,03131 10%

817397 3

0,5884 I

0,4321 3

0.3406 ae%

0.2877 ar

A2 % ERROR

-e2525

Q * b b 8 4

I ,a053

0.8242

0,6962

0,580s

0,4616

0.3782

8,3251

M A X INUM C D ERROR

IE!

5 %

3%

1

I %

I

1 %

1 %

I

M A X I HUM M A X IHUH M A X lHUM A 1 ERROR

2,6451 FO-5

1 ,6089 50

019686 13%

R, 'P IP7 5%

0.5663 3

0,4334 2

003476 1

0.2847 2%

A 2 %

i,aba8 13,2354

0,9.3lb 0,114CI

0.7437 631.0378

0,6355 0.01 42

a.5284 0.0QSbb

0-49 42 CI-00.32

0.3346 0,4313122

0.27 I 5 0,0822

c

1,2435

0,9589

0.7267

0,6294

0,5253

0.4177

0. 337 I

0,2752

a 0. I250

0.0884

a00486

Q.0227

0,o I27

a.am I

a. 00513 0 0055

ERROR

3

3%

2 %

I %

1 %

1 %

1 %

19:

F3-1 MEANS F A C T O R OF 3 e 1

Page 69: OF FWNCTIQ GAMMA-RAY BUILDUP F

-57-

abl le 5 (corit. ) I RON DOSE BUILDUP

P O I N T ISOTROPiC SOURCE 7 MFP F I T

MAX I MUM M A X I M U M M A X I M U M E I M E V I A I ERROR A2 B ERROR C 0 ERROR

I. 1.2373 2093 0-8026 0,0731 I % 0.8214 0.0684 2%

2. 0.8556 12% 0.6526 0.0342 58 Oo7020 0,0319 3%

3. 0.6691 9% Oe5338 0.0228 I % 0.5323 0,0384 I%

40 0.5403 7% 0.4366 c)*0175 I% 0.4366 0.0358 1 %

6. 0.4297 8% 0.3237 0.0178 1 % 0.3271 0,0457 1 %

0. 0.3391 8 % 0,2473 000154 13 0.2563 0.0464 1 %

I O . 0.2681 8% 0,1785 O o O 1 5 1 1 % 0,1876 0.0592 1 %

T I N DOSE BUILDUP

P O I N T I S O T R O P I C SOURCE 7 MFP F I T

M A X I MUM M A X I MUM MAX IMUM E4HEV 8 A ! ERROR A2 8 ERROR C 0 ERROR

0.5 0.5853 3% 0,5479 -00055 2% 0.5608 -00146 llg

I. 0.7199 6% 0,6153 0.0176 1 % 0,6219 0.0244 1 %

2- 0.6731 8% 015455 0,0215 I % 0.5498 0.0333 I %

3. 0 .5837 1 1 % 0.4284 0,0251 1 % 0.4379 0.~479 14:

4. 0.5146 12% 0.3420 0-0290 I % 0.3583 0.0601 1 %

8- 0.3317 17% 0.1371 0.0327 2% 0.1692 0-1103 f %

I O . 0. 2550 ? 6% 0.0945 0.0270 2% 0.1232 Oe1190 1 %

F 3 - I MEANS FACTOR O f 311

Page 70: OF FWNCTIQ GAMMA-RAY BUILDUP F

-5%-

l i ab l e 5 ( con t . ) TUNGS TEN DOSE BUILDUP

P O I N T ISCTRCPIC SOURCE 7 WFP F I T

M A X I HUM A 1 E R R O R

01 5 0,1903 8

I , 0,3817 5

20 0.4376 2

3 . 6,4173 5%

4, 004054 12

6 , 0 .3363 I7

8 , 0e25.24 16%

I O , a - 2 0 7 3 I 1 8

XI^^^ M A X I MUM A2 El E R R O R C 0 ERROR

269 -019076 2% 0 - 425 -00255 I f

6,0957 0.0281 2% 0,1245 8,1223 I

0,8748 0,0223 2% OeKl97b O m 1 2 3 8 I

W A X I MUM EIMEVI A 1 ERRQR

0.5 0. I 5 4 9 8 %

I , 0.2990 6 %

21, 013796 I

3, 0.3810 5%

4, 0,3523 10%

5, I 0,3219 13%

6 , 0,3[334 15

8 , [11.2&19 15%

119.. 0.1933 13

LEAD D O S E BUILDUP

P O I N T I SQTWQPIC SOURCE

F3. I MEANS FACTOR OF 3.1

Page 71: OF FWNCTIQ GAMMA-RAY BUILDUP F

- 59-

Table 5 (cont . ) URANI Ufir DOSE BUILDUP

POINT I SOTROPIC SOURCE

E(MEV9

005

I .

2.

3.

4,

6 -

8-

I O *

M A X I MUM A I ERROR

0-1054 7%

O.226b 7 %

0-3023 3X

0.3169 4%

0.3I1IO 7%

0-2571 1 2 1

0.20a1 12%

0.1621 1 1 %

? MFP F I T

R A X I M U M 8 ERROR

-.OU98 2%

-*a122 2%

-,0038 I%

Urn0069 I %

0,0136 4 %

0.0212 1 %

0.0201 1 %

0,0155 1 %

C

0. I025

o. 3204

0.3321

0.2814

0.2283

0. I 4 7 6

0.I08l

0,0798

MAX INUH ERROR

2%

2%

1 %

1 %

I %

13

1 %

I f

F3.1 MEANS FACTOR OF 3.1

Page 72: OF FWNCTIQ GAMMA-RAY BUILDUP F

-60-

Table 5 (coni;.)

MAX I MUM A ! ERRQR

3.7443 30%

1,9057 &O

1.0225 1 2 %

8-7303 7%

CI-5736 518

0.4329 69:

0.3376 6%

On2923 SO

ORCIINARY CONCRETE DOSE BUILDUP

POINT ISOTROP[C SOURCE 7 MFP FIT

A2

I , 3563

1 ,0980

a. 82 38

0.61 139

0.6 D 06

0.4667

0.3784

Q. 3344

I: E R R 6 P H 0 S P I4 0 R 0 U S t 0 N t R E 1' E DOSE BUILDUP

POINl- I S O T R O P I C SOURCE 7 MFP F I T

M A X I MUM A i ERROR

1.9407 F1.5

1,4657 30%

0.9264 10%

8,6996 4%

0,561 I 49

0,4399 2%

0.3493 2%

0,2827 3 %

M A X I M U M C D ERROR

A2

0,9330

0, a542

6). 7 4 8 I

0.61 98

0.J498CI

0,4119

0,3243

0-2574

F3.1 MEANS FACTOR OF 3.1

Page 73: OF FWNCTIQ GAMMA-RAY BUILDUP F

-61-

T a b l e 5

E ( H E V 1

0.5

I,

2.

3.

4.

60

80

I O .

(cont . ) M A G N E T I T E CONCRETE DOSE BUILOUP

POINT ISCTROPIC SOURCE

MAX I HUM A I E R R O R

2,3150 F1.5

1,6021 33%

0,9757 10%

0-7110 5%

0,5634 4%

0.4410 2%

0.3391 2%

0.2840 2%

7 HFP FIT

P A X l M U M A2

0.9510

0. 8847

0.7636

0.61 63

0.51 77

0.4200

0.31 27

0.2670

B

0.2295

0.12U7

0.0357

0.01 59

Oa0077

0.0035

Om0044

0.0029

ERROR

3%

316

2%

2%

I %

29:

I %

I %

M A X I MUM A t ERROR

1.4414 2 3 %

1.2066 21%

0.8740 IO%

0 .6556 6 1

0.5634 99;

0.4571 10%

0,3519 59:

0.2684 7 %

BARYTES CONCRETE D O S E BUILCl.JP

POINT ISOTROPIC SOURCE 7 PFP FIT

wax r wu pt A2 B ERROR

0.8769

a. 7599 0,6886

0.5345

0.4682

O.3344

0- 2836

0. 1894

0.0950

0.0752

OaO3 12

0.0204

0.01 60

o.0207

0.0I I 5

Q.0 I 3 3

C

l.fU49

0,9006

0.7770

0,6321

0.524 I

0- 440 1

0.3225

0.26a2

0

0.1221

0,0965

0.0380

flaC1194

OIUl19

-- 0004 0 . 0080 0.0096

M A X I M U M E R R O R

4%

4%

1 %

I%

2%

2%

f %

1 %

HAX I M U M C 0 ERROR

2% 0.9313

1% 0.7764

1 % 0-7006

3% 0.5508

3% 0.4413

1 % 0.3342

I % 0,2904

1 % 0,1990

0.0724

0.0737

0-0368

0,0289

0.04 f 8

0 ,0525

0.032 I

0,0495

1 %

2%

It

2%

3%

2%

I %

1 %

E301 MEANS F A C T O R OF 3.1

Page 74: OF FWNCTIQ GAMMA-RAY BUILDUP F

-62-

Table 5 ( con t . ) WATER DOSE BUILOUP

PLANE COLLIPtATEU SOURCE 7 HFP FIT

0.5 1.1802 0.2183 10% 1.4309 17.0891 3%

4, 0.5239 4% 915578 -.a057 2% 0,5775 - *0170 2%

I RON DOSE BUILDUP

7 HFP F I T PLANE COLLIN

M A X 1 MUM M A X HMCBM M A X IHUM E(HEWB A i ERROR A 2 B ERROR e 0

2- e3.7171 4% O,648! Q,0%14 2% 0 ,6698 0 , h l t l O I %

3. 0.5999 c 86 D,0[$85 2% 0,5633 0.0099 I

Page 75: OF FWNCTIQ GAMMA-RAY BUILDUP F

Tab le s (cont. )

-63-

T I M O O S E BUILDUP

PLANE COLLIMATED SOURCE 7 MFP F I T

E t M E V )

I,

2.

4.

6,

to.

E ( M E V )

0.5

I .

2.

3.

4,

60

$1

I O .

M A X I HUH MAXIMUM M A X I N U M A i ERROR A 2 8 ERROR C D ERROR

0.5999 43 0,6208 -00035 2% 0.6444 -00127 2%

0.5823 2 % 0.55178 0.01353 2% 0 ,5676 0.0038 2%

0.4560 7 3 0,3640 0-0155 1 % 0.3754 0,0322 1 %

0,3647 10% 0.2343 0,0219 I% 0,2524 0-0607 1 %

LEAD OOSE BUILDUP

PLANE COLLIMATEO SOURCE 7 MFP F I T

M A X I MUM M A X I MUM M A X I M U M A I ERROR A2 8 ERROR C 0 ERROR

0.1376 I O % o . 2 ~ -.0135 3% 0.2511 - . to49 29:

0,2723 10% 0.3633 -SO153 3% Uo3925 -a0632 2%

0.3440 4% 0.3871 -.0073 2% 0,4043 -00278 2%

0.2609 10% 0.1512 0.13185 2% 0,1749 0-0650 2%

0,2110 10% 13,1081 0,0173 2% c].12?2 0,0828 2%

0.1663 IO% 0,0848 O.Ot37 29; 0.1006 0,0821 2%

F3.1 MEANS FACTOR OF 3.1

Page 76: OF FWNCTIQ GAMMA-RAY BUILDUP F

Table 5

E ( M E V 1

a, 5 I .

2 ,

3 .

4-

6.

a.

IO.

-64-

(cont . ) URANIUM DOSE BUILDUP

PLANE C O L L I M A T E D SOURCE 7 MFB FIT

M A X I MUM A 1 ERROR

a.0961 7%

a.2029 931

0.2751 5%

8,2870 I %

0.2699 4 %

0.21340 0%

0.1834 8%

a . 1 4 m a%

M A X IMUH A2 FI ERRQR C a E R R O R

0.1582

Q e 2879

0- 3228

0.2000

0,2307

a. I 546

o. ta i7

ue076a

2%

3%

28;

I %

1 %

I %

2%

2%

U s I809

0,3137

11,3354

0,2067

U.2399

a. I (575

0.1 181

a*09C33

2%

2%

I %

1 %

1 %

1 %

2%

29

F3. i MEANS FACTOR OF 3.1

Page 77: OF FWNCTIQ GAMMA-RAY BUILDUP F

-65-

Tab le 6. Linear, Qiuadratic and Bergel- Coefficients for Energy Absorption Buil&up Formulas

Fitted over tile Range (0-7 MFP)

Page 78: OF FWNCTIQ GAMMA-RAY BUILDUP F

Table 6 (cont . ) WATER ENERGY ABSORPTION BUILDUP

P O I M T I SOTROPIC SOURCE

MAX a HUH A I ERROR

~ 1 , 0 9 5 6 ~3

4.3517 F2.2

2.0650 4 4

Is0581 1 1 %

Q.7881 3%

0 ,5956 I

611.4306 2%

Be 3437 3%

0 e 2 7 4 l 3

7 NFP F I Y

M A X I MUM A2

- 0 IO70

8.6651

9832

0,8472

Q, 74c5

0.5870

Q,4§75

0.3815

D.3075

6

I a 7033

I . 2727

I*8530

11,8300

0.7377

cS.fs881

0,4608

0, 3858

CJ.JISO

MAX I D

8.2546

0.2024

a, I 122

0,041 3

R . O l 1 3

0.002 1

-00 I I 6,

-.ai97

-a0238

ERROR

6%

5%

l s lg

2%

1 %

1 %

I%

1 %

1 %

ALUNI NUM ENERGY ABSORPTION BUILDUP

POINK I SOTROPIC SOURCE 7 MFP F I r

A ! ERROR

3,3193; F I . 7

1,8576 F l .4

1,0487 1 4

0-71t81 6 %

0 ,5719 3%

O.kI40 1 %

0,3191 1 %

0o2594 19

A2

1.1996

1.0517

0,8059

13.6556

8.5336,

as3970

0,3063

0.2484

f

1.4581

I .El825

0,7788

0,6496

0,5331e

Re3981

0,307 I

0,2495

0

0. I360

I3 . 0962 0.0505

0 e 0239

u.ai 17

a. 0065

0 . 0064 0 .OObS

ERROR

4%

3

3%

I X

1 %

1 %

I %

1 %

F3.1 MEANS FACTOR QF 3.1

Page 79: OF FWNCTIQ GAMMA-RAY BUILDUP F

Table 6

E ( M E V 1

0. 5

I.

2.

3.

4.

6 ,

8.

I O .

E 1 M E V )

0.5

I,

2.

3.

4.

6,

8.

I 0.

-6'7-

(cont . ) I RON ENERGY ABSORPTION BUILDUP

P O I N T I S O T R O P I C SOURCE

MAX I MUM AI E R R O R

2.5880 30%

1,6936 23%

0,9497 10%

a.6970 9 %

0.5396 7%

0.3741 7%

0.2744 7%

0.2179 7%

7 MFP F I T

MAX I MUM A2

1,5668

1.0932

0.7483

0.5592

0.4~4

0.2850

0, I 994

0. I5Ol

B ERROR

0.1718 3%

D . l O i O I %

13.0339 13

0.0232 1 %

0,0167 I 3

0.0150 I %

0.0121 I%

0.0114 I%

TIN

POINT ISOTROPIC SOURCE 7 MFP FIT

ENERGY A B S O R P T I O N BUILOUP

MAXI MUM A i ERROR

1.1016 7 %

1.1647 5%

0,8939 IO%

0.6299 12%

0.4684 129:

0,3234 54%

0.2261 I I $

0.1796 t o %

c 1.6700

1. I218

0.7551

O . S b l 7

13.4393

0.2883

0.2020

0. i 532

A 2

1,2165

1.0461

0.7123

0,4599

0.31 58

0. I628

0,1108

C.0833

M AX I MU M 3 E R R O R C

-.ai93 3% 1.2576

0.0200 3% 1.0833

0.0306 19 0.7087

0.0286 1 % 0.4672

0.0257 1 % 0,3237

o.0270 2% a.190)

0,0194 I % 0.1277

0.0162 1 % 0,0990

D

0.0726

a.0687

0,0384

0,0362

0.0346

0.0436

0,0495

0.0588

M A X I MUM ERROR

1 %

2 %

I%.

1 %

1 %

I %

I%

I 1

M A X IHUM D ERROR

-.a229 2%

0.0116 2 1

0,0390 1 %

0.0499 1 %

0.0617 1 %

0,0871 1 %

0.0941 1 %

0.0976 1 %

F3.1 MEANS FACTOR O f 3.1

Page 80: OF FWNCTIQ GAMMA-RAY BUILDUP F

-68-

Table 6 ( con t . ) LEAD ENERGY ABSORPTION

POINT IsorRoPrc SOURCE

MAX I HUM A ! ERROR

0,2591 2 0 4

0.5606 12%

0.5320 & $

0.3969 4 %

0.3047 84:

0.2607 10%

0.2133 1 1 %

U.1570 9 3

0.1194 8s

7 MFP F I T

WAX IMUH A 2 E! E RRQR

0-4407

0.7213

U,SS53

0.3124

0.21 26

O. I555

Q, IO60

0.071 I

0-0547

-.a305

-e0278

-. OUS9

13.0092

0,0155

0.01 7'p

13.0l8l

Re01 45

a.Ul09

M A X IMUM 4; a ERROR

- 0 1282

- 0570 -.0136

bJ.e9 I72

0.0502

0 a6565

0.O876

0.0630

0 . 0868

4

3%

2%

2

I %

I %

I %

1 %

2%

F.3-1 MEANS FACTOR OF 3 s 1

Page 81: OF FWNCTIQ GAMMA-RAY BUILDUP F

. -69-

T a b l e -{. Linear, Quadratic and Berger Coeffici.erits f o r Dose Buildup Formulas Fj-tted over t'ne Ra,nge

(0-20 ME'P)

Page 82: OF FWNCTIQ GAMMA-RAY BUILDUP F

Table 7 ( c o n t . )

-70-

HATER DOSE B U I L D U P

POINT ISOTROPIC SOURCE 28 MFP F I T

E ( H E V 1

0 .255

8.5

I,

2.

3.

*

6 ,

8 -

I a,

0" 5

I .

2,

36

b,

6.

80

10,

M A X I MUM WAX I M U M M A X IHUM A ! E R R O R Ai! B ERROR C 0 ERROR

13,0326 F5.6 -0.974ar 0187ar% F3 1.8035 0.1224 25%

0.2584 7% 0.3802 -.OD26 3% 0,3206 - *a139 2%

M A X I MUM M A X I MUM M A X BMUM A # ERROR A% B E R R O R C c1 ERROR

2.5385 F1.9 1.1185 0.0889 10 1,0831 O*c9535 9%

1.1928 30% 0,8751 8.0197 815 0.7869 c1.0266 6%

0.3697 5% 0.3395 L1.0019 1 % 61.3356 0.81758 I

F? i -1 MEANS F A t T O R OF 3.1

Page 83: OF FWNCTIQ GAMMA-RAY BUILDUP F

- 71-

!Cable 7 (cont.) I RON DOSE B U I L D U P

P O I N T I S O T R O P I C SOURCE 20 NFP F I T

H A X I H U M M A X 1 MUM MAX IMUH EtMEV 1 A I E R R O R A 2 B E R ROR C D E R R O R

0.5 2-3773 F 1 - 9 0.9019 0-0817 3% 0-9814 0aU5t8 79:

I. 1.8643 F l 06 0-9212 010586 7 % 0.8932 0,0460 7%

2, 1.1194 3 3 % 0.7423 0.0234 6% 0-71?3 0-0277 4 %

3. 0.8446 25% Om5840 0,0162 49: 0,5571 0.0261 4%

6. 0.6134 3 4 % 0.3201 0.0182 19: 0.3381 0-0368 39:

a, 0,5245 40% 0,2207 0.0189 3% 0.2603 0.0428 2%

IO. 0,4759 50% 0.1 143 0,0225 6% 0,1902 0,0553 1 %

T I N OOSE B U I L D U P

P O I N T I S O T R O P I C SOURCE 20 MFP F I T

M A X I MUM M A X I M U M M A X IMUM € ( M E W 1 A I E R R O R A 2 B E R R O R C D ERROR

0.5 0.5090 4% Oa515f3 -,0005 3% 0.5457 -e0063 3%

I. 0.8495 18% 0.6666 0.0114 3% 0.6378 0.0180 3%

2. 0.8521 2 5 % 0.5826 0.0168 3% 0 .5678 0.0254 3%

3. 0.8509 COO 0,4254 0,0264 1 % 0,4533 0,0388 3%

4, 0.8643F I 5 8 0.2845 0*0360 5% 0.3700 0-0518 3%

60 1,0786 F2.2 -,I374 0.0756 40% 0.2401 0.0891 2%

8 , 1.1907 F2.8 -04693 Om1032 F3 0.1669 0*1145 1 %

IO. 1.1075 F3.0 --6523 0,1094 F12 0.1 I90 0.1278 5%

F3- I MEANS FACTOR O F 3- 1

Page 84: OF FWNCTIQ GAMMA-RAY BUILDUP F

-72-

Table (coni;.) TUNGS TEN DOSE BUIL6)UP

P O I N T ISOiRQPlC SOURCE 20 MFP FIT

HAX I[ MUM E(F9EVB AB ERROW A 2 B ERROR c

a. 5 CS,1550 13% 0.2206 -.0854 53 R.2692

2 . ae4571 8% O14072 0.8037 3% 0.4163

LEAD DOSE BUILDUP

P O I N T ISOTROPIC SOURCE 2 0 MFP FIT

M A X I ~ U M M A X I MUM A ! ERROR A 2 B ERROR c

O a 5 0.1043 1 5 0.1391 -.ou43 5% 0,222e3

3. 0.5123 30 0.2990 19,0133 2% 0,3244

M A X I M U 0 ERROR

-.a447 5%

c1.01170 4%

0.1405 6%

0.1510 78

F 3 . 1 WEANS FACTOR OF 3,1

Page 85: OF FWNCTIQ GAMMA-RAY BUILDUP F

Table 7 (cont.) URANX UM OOSE BUILDUP

P O I N T ISOTROPiC SOURCE

E lMEU)

I.

2.

3.3

4.

6.

8.

IO.

M A X I MUM A I ERROR

o.aa12 1 1 %

0.1914 1 1 %

0,2838 5%

0-4081 20%

0.4993 43%

0.8088 F2.3

0.9323 F2.9

0.9203 F3.3

2 0 MFP FIT

M A X I M U H A 2 8 ERROR C

0.1262 --a037 5% 0,1635

0 , 2 5 5 6 -.a053 5% Q.2991

013185 -.OD22 29: U.3240

0.2614 c)*0091 2% 0.2781

0,1621 0.0210 6% 9,2273

-e2492 0 - 0 6 5 8 F2 a01426

-05357 0.0912 FS OoIOO4

-.6560 0-0980 F a 0-0721

M A X IMUW a ERROR

-.Q606 59

-.0385 5%

-a0084 2%

0.0234 I%

0.0475 1 %

0.1011 2%

0.1274 5%

0.4442 7%

F3-1 MEANS FACTOR OF 3.1

Page 86: OF FWNCTIQ GAMMA-RAY BUILDUP F

2 0 NFP F I T

A2

0.834 B

1,1821

0.9344

Q J I Srll

0.5652

0. b.440

0,34&5

003rJ15

FERROPWQSPWORQUS CONCRETE DOSE BUILDUP

POINT ISOTROPIC SOURCE 20 MFP F!T

A 2

1,1051

1 . 1 1713

0,7992

8,4488

0,4923

0.3622

0,2692

0. I971

WAX HHUN ERROR

12%

I I

5

5

4

4%

4

4

M A X I M U M D ERROR

u.10704 15

0.0481 10%

o.msla 3

8,13152 2%

0.0186 2%

0,0167 3

Do0196 4%

0.0287 3%

F 3 - 1 MEANS FACTQR OF 3.1

Page 87: OF FWNCTIQ GAMMA-RAY BUILDUP F

-75-

Table 7

E t M E V )

0*5

I .

2.

3.

4.

60

8-

I 0.

E1MEV)

0-5

I .

2.

3.

4,

6.

8.

IO,

(cor1t. ) MAGNETITE CONCRETE DOSE BUILOUP

P O I NT I S O T R O P I C SOURCE 2 0 WFP F I T

M A X I MUM A I E R R O R

4.2793 F2.5

2.3058 F I e 7

1.1752 25%

0.8098 15%

0.6263 10%

0,4781 7 %

0-3805 9 %

R-3399 12%

M A X I MUM M A X I M U M A2 B ERROR C 0 ERROR

1,4544 0.1756 23% 1.32116 0,0736 18%

1,2562 0,0652 20% 1-0651 0,0492 128

0.5280 0.0061 2% 0.5265 0.0108 I %

0.4257 0.0033 2% 0.4312 0*0062 2%

0,3195 0.0038 28 0.32n4 0,0106 2%

U.2428 0.0060 3% 0,2623 0.0156 2%

BARYTES CONCRETE DOSE B U I L D U P

P O I N T I S O T R O P I C SOURCE

M A X I MUM A I E R R O R

2,2489 F1.8

1,8761 F I . 7

1.1122 30%

0,8068 24%

0 ,6873 2 1 %

0.6277 30%

0,5574 40%

0.1943 509

20 HFP F I T

M A X I MUM A 2

1.1064

I .0022

Ro7591

0.604 7

0.4913

0,3420

0- I882

0,0936

0 E R R O R

0.0710 1 1 %

0.0543 14%

0.0219 4%

0.0126 6%

0.0122 49:

0.0178 2%

0,0229 in% U.0249 10%

C

I e o 183

0 , 8 5 5 5

0.7291

0.5673

U.4689

0,3542

U- 2806

0, I 949

0

0,0496

0.0495

0.0265

0.u222

Do0242

0.0355

U. 0409

0.0555

M A X I M U M ERROR

IO%

128

4%

4%

4%

4%

3%:

2%

F3.1 MEANS FACTOR OF 3.1

Page 88: OF FWNCTIQ GAMMA-RAY BUILDUP F

-76-

Table 7

E ( M E V )

0.5

I ,

2 .

3,

4.

6.

a.

E i H E V )

0 .5

1,

2.

3.

4.

6 ,

81

I O .

(cont . ) W A T f W DOSE B U I L D U P

PLANE C O L L I M A ~ E D sauacE

I RON DOSE B U I L D U P

PLANE C O L L I HAFED SOURCE

WAX I N U A I ERROR

1*2lnr2 20%

1,1161 203

0-8063 12%

Bc6634 l a 13.5465 12%

0.4SC16 1 5 %

8-3886 17X

8.340s 21

C

0,9558

0.8503

0 ,6595

u, 556131

0,4536

0.33% I

0,2587

CE-2a53

M A X ~~~~

a ERROR

0.098re 5 %

D,8216 3%

0,8162. 2%

0.8142 I

0,811811 285

0.0250 I %

0,0325 1 %

UaO404 I

F3.1 WEAMS FACTOR OF 3.1

Page 89: OF FWNCTIQ GAMMA-RAY BUILDUP F

Table 7 (cont . )

E(MEV8

I *

2.

4.

6.

IO.

EtHEVI

o m 5

I *

2.

3.

4-

6 -

8 -

I O ,

MAX I MUM A I ERROR

0.6238 4%

0.6381 91

0.4995 1 1 %

0.5651 430

0.4609 F1.6

-77-

T I N DOSE BUILDUP

20 MFP F I T IE COLLIHAffO SO lRCE

M A X I MUM MAXIMUM A 2 0 ERROR C D ERROR

0.5844 0,0032 4% 0,6203 -00002 3%

0.5235 0,0095 3% 0.5547 OeOllO 2%

0 ,3529 0,0176 2% Do3732 0,0344 1 %

0-1547 0.0338 8% 0.2490 0-0651 1 %

LEAD DOSE BUILDUP

PLANE COLLIMATE0 SOURCE 20 MFP F I T

M A X I MUM M A X I M U M M A X lMUM A I ERROR A2 fl ERROR C 0 ERROR

0.1202 10% 0.1927 -.0087 5% 0.2383 -008St 4%

0.2305 12% 0,3107 - -0066 6% 0.3642 -00394 5%

0.3334 5% 0-3545 -00057 4% 0.3855 -.0129 3%

0.3955 7% 0-3284 0.0055 2% 0.3448 0.0103 2%

0.4039 20% 0.2288 0.0144 39: 0,2622 0,0345 29:

0,4636 50% 0.0439 0,0346 13% 0,1672 0.0796 3%

0.4247 F1.6 -,0250 8-0311 16% 0-1216 0,0971 3%

0,3882 F1.6 -.0380 0.0318 16% 0e0950 Om1003 4%

F3.1 MEANS FACTOR OF 3.1

Page 90: OF FWNCTIQ GAMMA-RAY BUILDUP F

-78-

Table 7

E!MEV%

0.5

1 .

2.

3"

l e ,

6 ,

8 n

I O .

(cont . URANIUM DOSE ElUILBUP

PLANE COLLIMATED S O U R C E

M A X I paups A i E R R 0

0,6)825 l a 0,1777 1 2 %

cl.2813 5

&3%ae2 6 %

0.3330 15x

0.3783 38ri;

0.341 I b 7 %

0.2939 47%

A2

0. I 3 9 1

U.2127

8,2794

0,2556

i3.20rtT

0-0806

Q*I111217

-.a I 4 8

F.3-1 MEANS FACTOR OF 3.1

Page 91: OF FWNCTIQ GAMMA-RAY BUILDUP F

Tab1.e 8. Lir lear , Quadratic and Berger Coefficients f o r Energy Absorption Buildup Formulas

F i t t e d over -the Range (0-20 PFP)

Page 92: OF FWNCTIQ GAMMA-RAY BUILDUP F

Tab le 8 ( c o n t . )

-80-

HATER ENERGY ABSORPTION suiLauP

POINT ISarRupIc S O U R C E 20 MFP F I B

WAX I MUM F1 A x I MUM B

2 8075

0.7971

0.14-52

$3.02 I6

Be oa 38 0.00Cll

-. 0027 -.8030

- 0 002%

E R R O R

E r n

F3

1 1 %

P l g

2 8

I %

1 %

2’8:

3%

30%

24%

12%

5

2%

I %

1 %

2%

2%

A L U M I NUM ENERGY ABSORPTION RUliLQUP

POIrLIJ ISOTROPIC S O U R C F 213 MFP F I T

M A X I MUM M A X 4 MUN WAX INUM c

I 0 7 2 3 3

I .22aol,

9,8489

0.6 746

0.541 I

0,3945

0,31379

0,24%92

Page 93: OF FWNCTIQ GAMMA-RAY BUILDUP F

-81-

Table 8

E ( M E V 1

0.5

I.

2.

3,

4.

6.

80

I O .

E l M E V )

a. 5

I .

2.

3.

4,

60

8 ,

I O .

(conk. ) I RON ENERGY A B S O R P T I O N BUILDUP

POINT I SOTROP IC S O U R C E

M A X I MUM A I ERROR

4.3555 F2

2,5718 F1.7

1,2302 3 1 1

o.am0 25%

0.7098 2 7 %

0.5267 3 1 %

0,4121 33%

0.3742 40%

20 HFP F I T

M A X I MUM A2

I 6324

I .2621

0,8308

0.61 aa

0.4233

0.2857

0. I305

0. I 034

8 ERROR

0,1692 3%

0,0814 8%

0.0248 5%

0.Dl67 4%

0,0178 2%

O.0150 I %

0,0144 2%

0,0168 6%

T I N ENERGY ABSORPTION EUILOUP

POINT I S O T R O P I C SOURCE 2 0 MFP F I T

MAX I MUM A 6 E R R O R

1.0731 8 %

1,3409 16%

1.1007 26%

0,8999 40%

0- 7997F I 58

Oo768K I 84

0.7247 F2.2

0.6837 F2-4

MAX XMUM c 0 ERROR

I - 7887

1.2 192

0.7868

0.5847

0.4494

0,2975

0.2076

0. I565

A 2

I. 0838

l o l l 6 3

0,8284

0.5545

0.3073

-e 0552

-0235 I

-m3169

MAX I HUM B ERROR C

-*OOO? 6% 1.1873

0.0140 45 1.0819

0,0159 7% 0,7490

0.0215 89: 0.4909

0.0306 ba 0.3352

0.0512 25% 0.1931

0.0597 F2 0.1237

0.0622 F2.2 0.0930

0.0550

U.0466

0.0280

0.0255

0.0281

0.0353

0 0420

0.0528

7 %

89:

49:

4%

2%

3%

2%

1 %

MAX XMUM 0 ERROR

-a0069 4%

U.0134 3%

0.0245 4%

0.0380 9%

0,0534 8%

0.0820 2%

0.1030 2%

0*1148 4 %

F3.1 MEANS FACTOR OF 3.1

Page 94: OF FWNCTIQ GAMMA-RAY BUILDUP F

- 82 -_

MAXIMUP% A i ERROR A2 €4 E R ROW c B ERROR

a. 5 0,1925 23 0,3156 - . Q i U I 14% 0,4551 -,El753 IS

Page 95: OF FWNCTIQ GAMMA-RAY BUILDUP F

- 83-

Table 9. Cornparism of Average Percenta.ge Deviation Using Berger and Taylor Dose Forrmilas

- - ~~

Me an Per ceii t age Dev?i% i on 20 MFP Range 7 iWP Pa.nge

Medium We rger* Taylvr BergerM Taylor

Water 1c.o 3.6 1.2 3 *7 Aluminum

Iron

T i n

Tungs t en

Le ad

Uranium

2.5 2.8

2.1 2.5

1. .3 1.9 1. .7 1.6 2 *3 0.8 1.6 0.8

Ordinary concrete 4.2 2.9

E’errophos. concrete 3.2 2.6

Magnetite concrete 2.9 4 .2 Barytes concrete 2.6 3 .4

0.7 295

0.5 2.5

0.2 1.7

0 *3 1- .2

0.7 0.5

0.4 0.5

2 .o 4.0 1 .4- 3 . 3 0.9 4.8 0.6 3.7

*2O-MFP parameters used.

-x-XT-MFP parameters used.

Page 96: OF FWNCTIQ GAMMA-RAY BUILDUP F

-84-

PART 11 - App1.i cat i on of Bui 1.dup Fac to r s ?or Dis t r ibu ted Sources i n ?lane Geometry

Plane I s o t r o p i c Source Kerilel ... Using ..-.... . Berger Formula -.....l.l..-.... ~ ._.--..I-

A s an example o f an i n t e g r a t i o n making use of the Bwger form, the

ke rne l f o r t h e dose r a t e from an i s o t r o p i c , monoenergetic, pl-ane source

of s t r e n g t h 1 photon/cm2 -see is

where

p = dis‘iarice t,o source po in t on plane from perpendicular to

plane from d e t e c t o r ,

z = d i s t a n c e of d e t e c t o r from p?ane,

H = p “ f z ” ,

K(E) = fl-ux-to-dose f a c t o r a i energy E

Changing v a r i a b l e s and r ep lac ing B ( p R ) with t h e Berger formula yields

Then

where

(12)

m

dY ? .-Y y-n

n-l s E ( x ) = x n

A

Page 97: OF FWNCTIQ GAMMA-RAY BUILDUP F

o r , i n terrns of a plane bluildup f a c t o r ,

-(1 - D)p,z C e B(pz) = 1 -!- - 1-D ( p z )

I n t e g r a t i o n of Plane Kernel with Exponent ia l Source D i s t r i b u t i o n

Often a I-arge fraction of the r a d i a t i o n dose behind r e a c t o r and

s h e l t e r shiel .ds i s the secoridary gamm-a-ray dose due t o neutron capture .

If t h e spac ia l behavior of t he neutron f lux is f a i y l y well. known., t h e

gamma-ray dose may be calculated by i n t e g r a t i n g -the dose kerriel over t h e

source volume. I n a niariner similar t o that of t h e previoim ~ e c t - i ~ n and

with t h e geometry shown i n F ig . 39, the dose rate at t due t o 8 d i s t r i -

buted monoenergetic i s o t r o p i c SO-urce S ( x ) between a I t and. b is given by

b W

-PR -- - 2 KO S(x) dx 1 B(pR) dR

t

a t-x

Page 98: OF FWNCTIQ GAMMA-RAY BUILDUP F

-86-

Fig. 39. GEOMETRY OF INTEGRATION OVER EXPONENTIAL

SOU RC E 0 I STR I BUT1 ON

i

’1 --_. /-.-----

DETECTOR

Page 99: OF FWNCTIQ GAMMA-RAY BUILDUP F

-87-

b- t cn -pR k- B(pR) dR . (17 i- S ( t i- Z ) dz 2 1.1 0

Often -the neutron flux and consequent ly t h e secondary g;arrlma-ra,y

source may b e represented by an exponent ia l over n cer ta , in range.

can b e part; of 9 piece-wise i n t e g r a t i o n .

This

Le-t

where a i s the r e c i p r o c a l OS the product, of t h e gamma-1-ay absorp t ion

c o e f f i c i e n t and the neut ron r e l a x a t i o n lerigth.

Tnen

f

b- t m 7

0 IT-- I J

IJncol l ided Dose Rate

Using t h e Berger form f o r the buildup factoi", t h e i n t e g r a t i o n breaks

i n t o two p a r t s : t'ne uncol l ided and s c a t t e r e d terms.

from Eq. (18) j s :

Tile ulicoll.ided term

Page 100: OF FWNCTIQ GAMMA-RAY BUILDUP F

-88-

I n many cases of shi-eld design t h e d e t e c t o r i s a t t h e edge of t h e

s h i e l d ; tha t i s , b 5 t .

by p a r t s :

I n t h i s case Eq. 19 becomes upon i n t e g r a t i o n

If a > 1 t h e arzument of t h e

values may be deterznined from graphs such as those i n B1.j.zardl” o r

RockweL17 o r from Lables of t h e E i funct ion , no-Ling

func t ion i s nega t ive , i n which case t h e

N

- X

Page 101: OF FWNCTIQ GAMMA-RAY BUILDUP F

-89-

Them are some s p e c i a l cases in which arguments of the exponential

i n t e g r a l a r e zero.

evaluated as fo l lows .

!These cases resu1.t in indeterminates which may be

Case I

b = t, a # 1 ; a = 0, a # 0 .

Let y t - b

since

m

n=; 1

Thus

Let y = t - b .

Page 102: OF FWNCTIQ GAMMA-RAY BUILDUP F

- 90-

l i m

and

Case IV

b < t , a = I, a::: 0 .

t - - An - t-b '

and

K(E >so -ub -1J. t t Rn - -1 . (29)

t - b . To (t , 0 , t ) :I: [Ei ( p t ) - e ( p [ t - b ] ) f e

2cL

If' the d e t e c t o r i s loca ted wi th in the s h i e l d , it remains only t o

evaluate the second t e r m of Eq. 19. We cons ider the case for b ---f .

Page 103: OF FWNCTIQ GAMMA-RAY BUILDUP F

- 91.-

0 y+o 0

The r e s u l t f o r sources beyond .t i s then

-* t e

r o ( t , t , m ) = K ( E ) s - i n 1 1 t. a1 . 0 2IJ.a

E i t h e r h e a t i n g o r dose rake may be computed by mi l - t ip ly ing by the appro-

p r i a t e conversion f a c t o r s . 18 probably f i r s t published by Enlund.

Adding Eqs. 24 and 32 gives t h e heati-ng r e s u l t

Sca t t e red Dose Rate

The Berger bui ldup t e r m i s eva lua ted as follows:

(33 1

where T' ( t , a , b ) = s c a t t e r e d dose r a t e .

connect ion wi th Eq. 20 ( d e t e c t o r a t edge of slab), Eq. (33) ma.y be eva lua ted

as follows.

For t h e s i t u a t i o n d iscussed i n S

Page 104: OF FWNCTIQ GAMMA-RAY BUILDUP F

- 92-

L e t z = t - x . ‘Then

t - b Z

t-b

e -wt c 1 = K ( E ) S ~ - - --- 2 I . - 9 ) (1 -Tr-T&

For a i- D = 1,

For t h e d e t e c t o r w i t h i n t h e sl~ab, t h e contributlon from sources beyond

t remains -Lo be eva lua ted . Again we consi.der the case foin b --f m :

cn 50

t X 0

where z = x i- t . The s c a t t e r e d contribution from sources beyond t i s then

Page 105: OF FWNCTIQ GAMMA-RAY BUILDUP F

. -93-

This r e s u l t is added t o Eq. 36 f o r a d e t e c t o r w i th in t h e s l a b .

Graphed Funct ions for D i s t r i b u t e d Plane Sources

The uricoIlI.ided photon f lux soI.ution f o r Case I (Eq. 24) may be

w r i 1; ten

where

This f u n c t i o n is plotted i n F i g . 40 f o r various values of a. The scs t -

tered flux s o l u t i o n for t h e case of a = 0, b --2 t may be w r i t t e n

Page 106: OF FWNCTIQ GAMMA-RAY BUILDUP F

- 94-

where a’ - cx -t I).

The $I ( p t , a ‘ ) func t ion i s shown i n F ig . 4 1 for var ious values of

it i s r e a d i l y seen t h a t t h e formula t ion may a l s o be appl ied f o r a a’. l i n e a r buildup f a c i o r by s e t t i n g D = C .

For sources o f neuirons impinging on a semi- inf in ice medium w i - t h

an i n t e r f a c e n e t cu r ren t S , t h e garrmla-rzy jollrCe may be w r i t t e n

-kx S ( x ) = kJe

Then

whe1.e a = k /p .

The use of t h e 9 func t ions i.s due t o Cla,iborneL9 who devzl-oped

simi.1 a r eq-da’cions us ing polynomial bui-ldup f a c t o r s f o r tie case of the

d e t e c t o r wi.thin a slab which i s of i n t e r c s t i.n a heati.iig caicu1~at;ion.

Yne poiynomj.31 bui ldup f a c t o r i s

Page 107: OF FWNCTIQ GAMMA-RAY BUILDUP F

. - 95-

Tlie total f l u x is the sum

where

For the semi-inf i t i i t e medium,

2 4 e - q t - (1 + a)2 (2 - a ) e-pt - (1 +- a ) (1 - a ) p t e-pt , (53) % ( P t ) :=

4(1. - a)" (1 + a)2

Page 108: OF FWNCTIQ GAMMA-RAY BUILDUP F

- 96-

For a := 1. ,

C l a i b o r n e ' s art-i-cle (ref. 19) a l s o g i v e s the functions for slabs of

f i n i t e thickness as w e l l as averages OVei- the s l a b Lhickness.

These f i i n c t t o n s f o r the scmi- i r i f i i i i t e med.ium are plot-Led i n

F igs . 42-'-~5 f o r v a r i o u s values of a. Figs . 40-4-1 which were e v a l u a t e d f i i ~ sl.abs.

The f i r s t two may b e compared w i t h

Page 109: OF FWNCTIQ GAMMA-RAY BUILDUP F

0.soo

0.300

c

Ls L i (I) CL

0.200

0.100

0 0

-9'7-

ORNL-DWG 65-i1934 Fig. 40

THE SLAB FUNCTION qn (X,CY)

3

Page 110: OF FWNCTIQ GAMMA-RAY BUILDUP F

0. laoc

0.30a

..-. 25 c-e (r, a

0.200

0.100

0

-98-

ORN L- DWG 65-i 1935

Fig. 41.

3 9.0

Page 111: OF FWNCTIQ GAMMA-RAY BUILDUP F

-99-

X IMFPl

Page 112: OF FWNCTIQ GAMMA-RAY BUILDUP F

- 100-

ORNL-DWG 65-11937

Fig. 43. THE INFINITE MEDIUM FIJNCTION *, ( x , a )

1.00

0.800

0.700

0.600

- ?5 0.500 b-4 cn a.

0 . w

0.301:

0.20t

0.101

0 9.0 10

X (MFPI

Page 113: OF FWNCTIQ GAMMA-RAY BUILDUP F

-101-

Page 114: OF FWNCTIQ GAMMA-RAY BUILDUP F

-102-

ORNI-DWG 65.-11939

Page 115: OF FWNCTIQ GAMMA-RAY BUILDUP F

- 103 -

FAXT I11 - Applicatiori of Duildup Factors in F i n i t e or Lamina;Led Media

Although t h e scope of this r e p o r t was determined t o pri.msrrily

incI.ixde onl-y the bu i ldup f a c t o r PuricLioris f o r in.f-i.nite homogeneous media,

a s h o r t survey of work concerning f i n i t e o r lamina ted media ris i.i?elucd.ed

h e r e .

E f f e c t of Lezkage 20,21

The e f f e c t of lcrlkage from slabs i s given by Berger as a eorrcc-

t i o i i f ac - to r on tile s c a t t e r e d por-Lion of the Inuil.dup f 'actoy. Y'he r e s u l t s

were obtained by Morite C ~ Y L O cal .cul.atlons . Effec t of Lainiiiations

Empir ical formul-as based on Monk Carlo d a t a have been given by 23 , 2 J.C Kalos'* f o r dose r a t e and by Bowman arid Tru'ney

formulas prescrj-be how homogeneous medriuni bu i ldup f a c t o r s may be covLbined

to y i e l d val.u.es f o r 1-a;mi.nated media,.

for hea t ing . These

S l a n t Pe ne t rat ion

Empir ical formulas, aga in based on Monte C a r l o data, have been given

by Pieper and Beach25 f o r cal.cu1atirig t h e e f f e c t o f s l a n t incidence.

Sinii.l.ar, but more coq) l - i ca t ed , f'omml as are given by Rexroad arid Schrnoke 26

f o r calcul .a t ing dose rate from f a l l o u t i n a blockhouse.

Ta,bulated resir1 ts 1'rom motnenis niethod c a l c u l a t i o n s are given by

Spencer and Tm&in 27720 and from Monte Car lo c a l c u l a t i o n s by Burre l l and

Cr ibbs . 29

The author i s g r a t e f u l t o E. E . Hranstetter of t'ne ORNL Mathematics

Div is ion f o r p?og:ramning t h e l e a s t - squares code which produced the CO-

e f f i c i e n t s of Tables 5 - 8 a i d t o X. C. CJaihorne for many bel-pful d i s -

cuss ions and f o r h i s equzt ions prior t o nub l i c s t ion .

Page 116: OF FWNCTIQ GAMMA-RAY BUILDUP F

- 104-

1.

2.

4.

5.

6.

7.

8.

9.

10.

1-1.

12.

14.

11. Goldstein and J. E. Wj.1-kins, Jr . , -. Calcula t ions of t h e Pene t r a t ion of Gamma Rays, NYO-3075 (1954).

H. Goldstein, Fundamental Aspects o f Reactor Shie ld ing , p . 218, Addison-Wesley, Reading, Mass., 1959.

J. J . Taylor, Applicat ion of Gamma Ray Ruildu!) Data Lo Shie ld Design, WAPD-RM-217 (19511).

G. L. Strobel., --__. Nucl. Sci. .- Eng:., l1(4), 450 (1961.).

S. Buscaglione and H. Manzini., Sui F a t t o r i D i AccumuAazj.one: Coef- __.- f i c i e n t ? De l l a Formula D i J. J. Taylor, ~ ' i ' / ~1 (65)7 (1-965) o r t h e Engl-ish t rans la t i -on Buildup Fac to r s : Coeff ......-.. .. i c i e i l t s of t he J. J. Tay3..or E q . , OI<NL-tr-80 (Rev. ) (1965).

R . TJ. Walker and M. Grotenhuis, __._.- A Survey of Shie ld ing Constants f o r ..... .- Concrete, ru~i,-644j ( I 961).

!i'. Rockwell, ed., Kexctor Sh ie ld ing Design .- Mamial, New York, McGraw- H i l l Book Company, 1956.

...... _ _ ~

A. Honig, Dose Buildup Fac tor €or Concre Le, OKNL-tr-502 t r a n s l a t e d from Kernt echnik, II_ 6 ( 9 ) , 3 93 .I 99

M. A. Capo, Polyfiomial Approximation of Gamma Ray Buil.ilup Fac to r s f o r a Point Xsotropi-c Source, - ~ ~ ~ ~ - 5 1 6 - ' T 1 9 5 8 ) .

M. L. Tobias, D. R. Vondy, and M. P. Lei izke, Nightriiaxe - &r IBM-7090 ........ .-

Code f o r t'ne Calculati-on ..-_ of Gamma Heating i n C y l i n d r i c a l I__. . Geometry, ORNL-3 1 98 ( 19627-I

S . Buscag:l1:.o:tie and R . Manzini, Sui F a t t o r i ....... D i Accurnulazjone Del Calcestruzzo: Coeff ic ien t5 Dell-a ........ Rappresentazione Pol~iorniale, --- CEC-94 or t h e Engl-ish Trans l a t ion On t h e Build.up ........... of Concrete: CoefPLcients of t he Polynomial Representat ion, ~ l _ _ _ ~ ORNL.-%-t;r-jl19 (1965 ). --

M. J. Berger, Proceedings of Shie ld ing Symposium held a t t h e Naval Radiologica3 Defense Laboraiwy, ~ U S W L ......... Reviews and Lectures NO. 29, p. 41 (Wm. A. 13. Chil'con, D. Xoloviak, and 1,. K. Donovan, Determinat ion of Parameter i n an :Empirical Func'ciori f o r Buildup Fac to r s f'or Various

-- Photon Energies , U S N C E L - ' P N - j ~ 9 5 ) (1960).

A. R i id lo f f , The U s e of Buildup Fac to r s i n Ca lcu la t ing Ganirna Radia- ti on from Plane Sources Behind Absos-ber of F i n i t e Extension, Atomkernenergie, 3, I151 (1 964).

Page 117: OF FWNCTIQ GAMMA-RAY BUILDUP F

-105-

15. A. B. Chil.ton, Two-Pammeter Formula for Point, Source Buildiup Fsc- t o r s , Nucleoiiics, 23 ( 8 ) , 119-122 ( A u g u s t 1965).

1-6. J. TI. Ibibbell, A Pover S e r i e s Buildup Fac to r Formulation. Appl-ica- t i o n t o ReclxmgS?nlxr and. O f f - A x i . s Disk Soui-ee Problems, J. Res. NBS, 67c, 4, 291-306 (1.963).

17. E. P. Blizard and T,. S . Abbott, e d i t o r s , Reactor IIandbook, See. Ed. , Vol. 111, B r L B, Slii.el.ding, p. 148, In t e r sc i ence , New York.

18. 11. I;. F. Enluncl., Ene:t.gy Absorption - of Capture Gammas , ORNL CY-52-6-99 See A l s o E. P. B1izar.d and 1,. S. Abbo’it, e d i t o r s , (Suppl. I.) (1952).

op. cit., p. 1-79.

1~9. H. C . Claiborne, p r i v a t e cornmuni.cation, ~ 1 . ~ 0 a r t i c l e i n IAEA Engineer ing Compendium on Radia t ion Sh ie ld ing (to be pub1.i shed).

20. Cited by Goldstei.11, I-I., Fundamental. A-spects of Reactor Shri.el.dj.ng, p. 212, Addison-Wesley, Reading, Mass., 1959.

21. M. 3. Eerger, and J. Doggett, Re f l ec t ion and Transmission o r Gamma Xadia’iion by- Barrieys : Semi.sna1yti.c Monte Car1.o Calcu la t ions , J. Xes. of BBS, ~6(2), 89-98 (1956).

22. H. CToldsl;ein, op. c i t . , p. 225-226.

23. E. P. K-iza rd and L. S. Abbott, e d i t o r s , Reactorr Handbook, 2nd Ed., VoL - 111, Part 5, Shield.ing, p. 1.75-1-76, In te rsc ie i ice , New York, 1962.

24. L. A. Bowman and D . K. Trubey, Deposl t ion of Garma-Kay Heattrig i n S t r a t i f k d Lead ,md Water Slabs, ORNL CF-58-7-99 (1958).

25. A. G . Pieper and I,. A. Beach, S t o c h a s t i c E s t i m a t e s of t h e Penetrat ior i of Gamvift Xays throiigh Slab Sh ie lds , NRL-5981. (1963 ) .

26- R . E. Rexroad, M. A. Schmoke, and Ii . J. T i l l e r , Point-t,u-Poirlt Kernel Analysis of ar, Expe rj-rflent t o Determine W a l l Pene t r a t ion of a Square- based Coricrete S t r u c t u r e by Gamma Radiat ion, Nucl. S e i . Erig., 20(1) 66-79 (1964).

27- L. V. Spencer and J. C . -zarlkin, S l a n t Pene t r a t ion of Gamma-Rays i n I I O , - NBS Report 5344 (1958).

0 2 ~ . L. V. Spencer and J. C . LanikAn, Sl.a.nt Peneirat,ion of Gamma-Rays in Concrete, NBS Repor t 6591 (1959).

290 M- 0. B u r r e l l and D. L. Cribbs, A Monte Carlo Gal-culatiun o€ Gamma Ray Pene-Lration through I r o n Slabs , NR-82, Vol.. I1 (lg10).

Page 118: OF FWNCTIQ GAMMA-RAY BUILDUP F
Page 119: OF FWNCTIQ GAMMA-RAY BUILDUP F

OR!!TL-RSIC- 1.0

D i s t r i h u t i on

1. 2 . 3 * 1-1 . 5. 6 . 7- 8 . 9 . 10. 11.

1.2-1.4.

15 - 16.

17 - 1.8 . 19-

20-244 m

2h5-694. 695

E. P. B ~ ~ z u C I F. C . Maienschein W. H. Jordan Arthur Reetz, ?USA Headquarters, Washington, D. C . William Alfonte , DASA, Washington, D . C . P h i l Hemmig, Division of Reactor Dev. & Technology, US,W,C R . E. Bowman, DTlE G. Dessauer (Consul tan t ) M. L. Goldberger (Consul..tant) M. H. Kalos (Consul tan t ) L. V. Spencer (Consu?.t;ant; ) Lab o r at ory Records Departmerit Laboratory Reacords, RC ORNL Patent Off ice Central Research Library Doc ime lit R e f e I' eric e S e c t i on RSIC D i s t r i h u t i on Div is ion of Technical Inf ormatior? Extension Research and Development Div is ion (ORO)