A .Nuclear Cross Section hand book.pdf

7/21/2019 A .Nuclear Cross Section hand book.pdf

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LA-11711-M

Manua l

C3

. ; , ,

, .

: :; . , ,

EPRODUCTION

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,:,


2/292

Ed ited by Pa tr icia W. Mend i.us, Group 1S-11

Prepared by H elen By ers, Group X-6

I

Art

A ff ir ma ti ve A ct ion / E qu al Op por tu ni ty E mp loy er

This reportwas prepared as an account oj work sponsored by an agency of the

United States Government. Neither the United States Government nor any agency thereof,

nor any of their employees, makes any warranty, express or impli ed, or assumes any legal

l iability or responsibility for the accuracy, completeness, or u s ef u ln e ss o f a n y information,

ap~ratus, product , or process disclosed, or represents that i ts u se would not infringe

prmrately owned rights. Reference herein toany specific commercial product, process, or

service by trade name, trademark, manufacturer, or otherwise , does not necessarily constitute

or imply its endorsement, recommendation, or faooring by the United States Government

or any agency thereof. The views and opinions of authors expressed herein do not necessarily

s t a te o r r ef kct t h os e of the United Sta tes Government or any agency thereof .


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LA-11711-M

M anual

Llc-705

Issued: December 1989

A Nuclear Cross Section

Data Handbook

H arl O M . Fi sher

Los

Mm-log

L os Ala mos Na t ion al L a bor a tor y

L os Ala mos,New Mexico 87545


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CONTENTS

P RE F AC E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

ACK NOWLE D G ME NTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

AB S TRAC T . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

I .

I I .

I I I .

I V.

v.

v.

VI .

INTROD U C TI ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

H AND B OOK CONTE NTS . . . . . . . . . . . . . . . . . . . . . . . .

ARRANG E ME NT OFTH E DATA . . . . . . . . . . . . . . . . . . .

A. Ta bula rDa ta . . .

B . G ra phics D a ta . .

H E ATI NG N U MB E R S

D I S C U S S I ON . . . . .

RE F E RE NC E S . . . .

AP P E ND IC E S . . . .

A. E xpla na t ory Not es

B . C ross S ect ion Not es

TABLES:

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

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

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

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

TAB LE I . I sot opes a nd E lement s C ont ained I n This Volume

TAB LE I I . List of E lement s Alpha bet ica lly . . . . . . . .

TAB LE II I . List of E lement s by At omic Number . . . .

TAB LE IV. List of Rea ct ion Types or MTs . . . . . . .

TAB LE V. E va lua t ions Wit h Nega t ive H ea t ing Numbers

H -l . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

D -2 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

T-3 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

H e-3 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

H e-4 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

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vii

vii

1

1

3

5

6

6

6

8

11

276

276

277

13

14

15

16

17

18

20

22

24

26


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Li-6 . . .

Li-7 . . .

B e-7 . .

B e-9 . .

B -10 . .

B -I I . .

c

. . . .

C-12 . .

C-13 . .

N-14 . .

N-15 . .

0-16 . .

F-19 . .

Na -23 .

Mg . . .

Al-27 . .

S i . . . .

P -31 . .

S -32 . .

cl . . .

Ar . . .

K

. . . .

Ca . . .

Ti . . .

v . . . .

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28

30

32

34

36

38

40

42

44

46

48

50

52

54

56

58

60

62

64

66

68

70

72

74

76

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UL .

Mn-55

Fe .

co-59

Ni .

Ni-58

C u .

G a .

As-74

As-75

Kr-78

Kr-80

Kr-82

Kr-83

Kr-84

Kr-86

Y-88

Y-89

Zr .

Nb-93

Mo .

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

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Rh -lo3 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Aver a ge Fission P r oduct from 235U . . . . . . . . . . . . . . . . . . . . . . .

Aver a ge Fission P roduct from23gP u . . . . . . . . . . . . . . . . . . . . . . .

Ag . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

78

80

82

84

86

88

90

92

94

96

98

100

102

104

106

108

110

112

114

116

118

120

122

124

126

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Ag-107 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Ag-109 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

C d . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

S n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Avera ge F ission P roduct . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Xe .,

Xe-134

Ba-138

Sm-149

E u . .

Eu-151

Eu-152

Eu-153

Eu-154

G d . .

Gd-152

Gd-154

Gd-155

Gd-156

Gd-157

Gd-158

Gd-160

Ho-165

H f . .

Ta -181

iv

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128

130

132

134

136

138

140

142

144

146

148

150

152

154

156

158

160

162

164

166

168

170

172

174

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Np-237

Np-238

P u-237

P u-238

Pu-239

Pu-240

P u-241

P u-242

P u-243

Am-241

Am-242

Am-243

Cm-242

Cm-243

Cm-244

Cm-245

Cm-246

Cm-247

Cm-248

B k-249

cf-249

cf-250

cf-251

cf-252

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

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228

230

232

234

236

238

240

242

244

246

248

250

252

254

256

258

260

262

264

266

268

270

272

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PREFACE

When work on this handbook commenced nearly three years ago there were two

fundamental goals that had to be addressed. First was providing the users of MCNP

and its family of codes a current, portable, complet e(all of the recommended data

comprising the MCNP library should be included), qualitative, yet concise refer-

ence document containing isotopic information, evaluation information, the origin of

the data, and its representation in both a tabular and graphical form. Secondly, and

perhaps just as important, was the production of this document in a manner such

that (a) the update of a single nuclide or several nuclides could be performed in a

matter of minutes, and (b) the entire document could be updated and a new edition

produced in a matter of weeks (depending of course upon the amount of upheaval

in the MCNP data library). With the inclusion of the tabular data, pie-charts and

cross-secton curves for the 129 evaluations which are the source of the default cross

sections for MCNP, plus the accompanying explanatory information pertinent to each

evaluation, we hope that the first objective has been achieved. Discerning a met hodol-

ogy which would facilitate the accomplishment of the second objective was extremely

dficult. Ideally, one wants a program which can be started and left unattended, while

the desired data is automatically generated, formatted, and assimilated. Such an idea

may seem a little far-fetched at first glance; however, when viewed in greater detail,

one finds that the major prevent atives from having such a program are syst emit. Ever

cognizant of the above factors, a Fortran Command Language (FCL) program (.FLO-

GIN) was written to accomplish the task previously alluded to. Although the program

cannot functionally perform all of the tasks required to make the generation of the

handbook completely automatic, it comes as close as presently possible, considering

the system constraints and the disparity of the data. To circumvent many of the con-

straints imposed by the system(s) a small C-Shell program (MKHBK) was written to

provide a direct communicative liik between the CTSS and UNIX computing environ-

ments. In actuality, both .FLO GIN and MKHBK are controllers; the former allows

one to automate repetitious processes, whereas the latter removes the task of manu-

ally transporting, assimilating and processing large numbers of files and/or data from

system-to-system. These controllers are very general in scope and simple in their ap-

plication, and it is precisely this generality and simplicity which make them so powerful

and instrument al in the accomplishment of the second objective mentioned above.

ACKNOWLEDGMENTS

The successful completion of any project of this magnitude requires the assistance

and cooperation of many people. Although it is practically impossible to individually

thank all the contributors from throughout the Laboratory for their helpful contri-

butions, there are a few individuals whose assistance merits special attention. In

particular, I would like to thank Robert Hotchkiss for the many hours of discussions

and heated arguments that we had on formatting the data; for introducing me to FCL

and holdlng my hand while I became familiar with it, and for his special effervescence

which made a somewhat intractable task a great deal of fun. I also owe a special

debt of thanks to my colleagues Robert L ittle and Robert (Big Bob) Seamen. The

former for his many reviews of the document, constructive comments, corrections and

vi i


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criticisms; the latter for his modification of the FICHE code which facilitated the for-

matting of the text, for gathering and assimilating the necessary headiig information

and for his special brand of fastidiousness and attention to detail whkh assured

t h a t

the quality and completeness of the document would be maintained. Lastly, I thank

Mrs. Helen Byers for the many hours we spent discussing ~ in general and its use

and application to the

Handbook

in particular.

. . .

Vlll


13/292

A NU C LE AR C ROS S S E C TI ON D ATA H AND B OOK

by

HarlO M. Fisher

ABSTRACT

Isotopic information,

reaction data, data availabilityy,

heating numbers, and evaluation information are given for

129 neutron cross-section evaluations, which are the source

of the default cross sections for the Monte Carlo code

MCNP. Additionally, pie diagrams for each nuclide display-

ing the percent contribution of a given reaction to the the

total cross section are given at 14

MeV,

1 MeV, and ther-

mal energy.

Other information about the evaluations and

their availability in continuous-energy, discrete-reaction, and

multigroup forms is provided. The evaluations come from

ENDF/B-V, ENDL85, and the Los Alamos Applied Nuclear

Science Group T-2. Graphs of all neutron and photon pro-

duction cross-section reactions for these nuclides have been

categorized and plotted.

I. INTRODUCTION

C ross-sect ion da t a a r e t he essen tia l

input t o a ll ra dia t ion t ra nspor t codes;

a n d a bsolut ely n ecessa r y com pon en t of t he

indeed, cross sect i on s m ust exist for ever y

elem en t a n d isot ope w h ich a ppea r in a t ra n spor t pr oblem in or der t o effect a solut ion

of t ha t problem. I t is t he cross sect ions w hich cont a in in form a tion a bout w ha t

ha ppens t o t he neut rons a nd phot ons w hen t hey collide w it h a toms of t he ma teria l

t hr ou gh w h ich t hey pa ss. F ur th er mor e, t he ph ysics in for ma t ion d ist in gu ish in g on e

elem en t fr om a n ot her is a lso cen t a in ed in t he cr oss sect ion s.

Neut ra l-pa rt icle t ra nsport codes such a s t he Mont e C a rlo code MC NP l need

n eut ron in ter a ct ion , n eu tr on -in duced ph ot on pr od uct ion , a n d ph ot on in ter a ct ion

cr oss sect ion s t o per for m t h e m a ny a n d va r ied eva lua t ion s a n d ca lcu la t ion s t o w h ich

t he a scr ibe. Th is H a nd book pr ovid es in for ma t ion a bout t he n eu tr on in ter a ct ion a n d

ph ot on pr od uct ion cr os s s ect ion s for t h e ev a lu a tion s on w h ich d efa u lt cr os s s ect ion s

for MC NP a re ba sed, These n eut ron cr oss sect ion s a re com piet e in t he sense t ha t

cr oss sect ion s, a n gula r dist ribu tion s, a n d secon da r y en er gy dist ribut ion s for ea ch

r ea ct ion a re a va ila ble; cross sect ions for producin g phot on s a long w it h t he en ergy

1


14/292

a nd a ngula r dist r ibut ions of t he induced phot ons a re a lso ca rried on t hese files;

h ow ever , n ot a ll n eut ron cr oss-sect ion set s in clu de ph ot on pr odu ct ion da t a .

E ach neut ron cross-sect ion set is genera ted from a n eva lua ted da ta set . An

eva lua t ed set of cross sect ion s is pr oduced by a na ly zing experim ent a lly m ea sured

cross sect i ons a nd combining t he da ta w it h t he predict ions of nuclea r model ca l-

cula t i on s in a n a t tem pt t o ext ra ct t he m ost a ccura t e cross-sect ion inform at ion . I n

a n eva lua ted da ta set no a mbiguit y is a llow ed; t his simply mea ns t ha t a decision

ha s been rea ched on w ha t t he cross sect ion for ea ch rea ct ion should be a nd w ha t

t he seconda ry energy a nd a ngula r dist r ibut ions should be. The ma jor it y of t he

da ta present ed in t his

Handbook

comes from Version V of t he America n na t iona l

E ND F/B (E va lua t ed Nuclea r D at a F ile/B ) syst em .

2$3Th es e cr os s s ect i on s a r e s up-

plem en ted by ev a lu a tion s fr om t w o ot h er sou rces : t he L a w ren ce L iv er mor e N a tion a l

La bora tory s E va lua ted Nuclea r D at a Libra ry (E ND L)4 a nd eva lua t ions from t he

L os Ala m os Applied N uclea r S cien ce G r ou p T-2. O ld er ev a lu a tion s a cces sible fr om

ot her sou rces h a ve n ow essen tia lly been ph ssed out .

F rom a n y on e eva lua t ed da t a set , sever a l set s of cr oss sect ion s ca n be gen er a ted .

F or t he Mont e C a rlo code MC NP t he eva lua t ed da ta a re processed int o AC E form at

(AC E is a n a cronym for A C ompa ct E ND F) descr ibed in Ref. 1. C ross sect ions

in AC E forma t a re given a nd used a s cent inuous-energy funct ions, F or use w it h

d iscr et e or din a t es t ra n spor t cod es like 0N E DAN T5 a n d TWOD AN TG , m uh igr ou p

sca t t er ing ma tr ices must be ca lcula ted from t he eva lua ted da ta . The forma t of t he

mult igroup da ta is descr ibed in Ref. 7. These mult igroup sca t t ering ma trices for

t he S N met hod a re used a s t he source from w hich mult igroup da ta a s descr ibed

in Ref. 8 a re genera t ed for input t o MC NP w hen it is run w it h t he mult igroup

opt ion. At Los Ala mos w e ha ve cross sect ions in bot h point w ise a nd mult igroup

for m a va ila ble fr om t he sa m e eva lua t ed da t a sou rce; t his m a kes possible m ea n in gful

com pa r is on s bet w een t he cen t in uou s-en er gy M on t e C a r lo, m ult ig rou p M on t e C a r lo,

a nd S N m et hods.

I n AC E forma t t he cross sect ions for a ll rea ct ions a re provided on a single

en er gy gr id. Th e gr id is su fficien tly d en se t ha t lin ea r -lin ea r in t er pola t ion bet w een

point s repr oduces t he eva lua t ed cross sect ion s w it hin a specified t oler ance t ha t is

gen er a lly on e per cen t or less.

All cr oss-sect ion t a bula t ion s given in t he eva lu at ed

da ta w it h sem i-log or log-log int erpola t ion schem es a re lin ea rized. D ependin g on

t he lin ea r iz a tion t oler a nce, but pr im a rily on t he n um ber of u nr esolved r eson a nces

a n d t h e r es on a n ce r econ st r uct ion t oler a n ce (g en er a l ly 0.5$%0r b et t er ), t h e r es ult in g

energy gr id ma y cont a in a s few a s 250 point s (e. g., H -1) or a s ma ny a s 22,500

point s (e. g., Au-197). The or igina l AC E-forma t libra ries - t hose most closely

r epr esen tin g t he in ten tion s of t he eva lua t or s - ca n be ver y lon g files. Th in ned files

w er e pr epa r ed for t he sa m e eva lua t ion s in su ch a w a y a s t o pr eser ve t he fla t -w eigh ted

in tegr a l of t he t ot a l cr oss sect ion t o w it hin 0.590. Th er e a r e a lso d iscr et e-r ea ct ion

cr os s-s ect ion files in w h ich t h e poin tw is e r ea ct ion cr os s sect ion s h a ve been a v er a ged

over 262 energy groups using a fla t w eight funct ion. Thus, for Mont e C arlo cross

sect ion s it is pos sible t o gen er a t e m a n y d iffer en t set s d epen den t on t h e lin ea r iz a tion ,

resona nce-r econ st ruct ion , a nd t hinn in g t oler ances, t o sa y not hing of t he r an ge of

t em per a tu res t o w h ich t he cr oss sect ion s ca n be br oa den ed. Wit h m ult igr ou p cr oss

2


15/292

s ect ion s t he pr oblem is com pou nd ed beca u se of t he v a riou s en er gy g rou p s tr uct ur es

a n d w eigh t fun ct ion s w h ich ca n be used in t he cr oss-sect ion colla pse.

Th e con tin uous-en er gy AC E cr oss sect ion s a n d m ult igr oup cr oss sect ion s w er e

pr ocessed fr om E ND F/B -V a nd G r oup T-2 eva lu at ion s usin g m od ules of t he NJ O Y9

n uclea r d a t a pr oces si ng s ys tem . Th e cr os s s ect ion s f rom E N D L-85 w er e pr oces sed l

using t he MC P OINT code w hich is a va ila ble in t he OME G All code pa cka ge.

This

Handbook

con t a in s plot s of r ea ct ion s f rom t h e or ig in a l con t in uou s-en er gy

cr oss-sect ion set w hich m ost fa it hfully r epr oduces t he in ten t i on s of t he eva lua t or .

An index t o a ll ot her represent at ions of t ha t eva lua t ion a va ila ble in cont inuous-

ener gy or m ult igr oup form at , a lon g w it h a det ailed descript ion of t he rea ct ions in

ea ch ev a lu a tion is a lso pr ov id ed .

Only one eva lua t ion is plot ted for ea ch isot ope or element ; a s ca n be seen from

Appendix G of Ref. 1, t here a re ma ny ca ses w here more t ha n one eva lua tion is

a va ila ble; t he eva lua tion chosen is t he one w e believe t o be t he best a nd most

curr ent . These eva lua t ions cor respond t o t he defa ult cr oss sect ions w hich a re ob-

t a ined w hen MC NP is run in a defa ult cross-sect ion mode, a nd t hey correspond

t o t he eva lua t ions fr om w hich t he a forement ioned m ult igroup cross sect ions w er e

generated.

Th e pr oduct ion of t his

Handbook

is in d ir ect r espon se t o t he expr essed d esir e of

MC NP users t o ha ve r ea dily a va ila ble a con cise pa cka ge of in for ma t ion w it h w hich

t o ch a ra ct er ize t he ph ysica l pr oper ties of t he m a ter ia ls used in t heir ca lcula t ion s.

Th e cr oss-sect ion plot s a r e pr esen ted exa ct ly a s on e w ould fin d t ha t in for ma t ion on

t he da ta libra ries ma int ained by t he Nuclea r D at a Tea m in G roup X-6; no a tt empt

ha s been ma de t o rem ove a ny of t he im per fect ions in herent t herein .

II. HANDBOOK CONTENTS

This document cont a ins 129 set s of t a bula r da ta , pie-cha rt s a nd plot s of t he

n eut ron in ter a ct ion , a nd ph ot on -pr oduct ion cr oss sect ion s for t he elem en ts list ed

in Ta ble I . The chemica l symbol ident ify ing a cer t ain element or isot ope is list ed

iir st , follow ed by t he n uclid e id en tifier n a me or ZAI D.

The t a bula r da ta list s t he sour ce of ea ch eva lua t ion; t he a ppropria t e refer ence

for t ha t s ou rce, t he a v a ila ble d a ta f or t he eva lu a tion , is ot opic in for ma t ion , eva lu a tion

i nf or m a t ion , a n d r ea ct ion i nf or m a t ion .

The source refers t o t he t a pe or file from

w hich t he eva lua ted da ta w a s t a ken - t ha t file w hich w a s input t o t he NJ OY code

or t o MC P OI NT. The reference is tha t document in w hich t he eva lua tion is best

described a nd w hich ca n be referenced in t he lit era ture. Tw o document s a re fre-

q uen t ly r efer en ced in com plet ely . Th e com plet e bibliogr a ph ic cit a t ion for E ND F -

201 is Ref. 2; t ha t for E ND F-201 S upplement I is Ref. 3. All of t he cr oss-sect ion

s et s d er iv ed fr om a s in gle eva lu a tion a r e list ed u nd er

data availabilityy. Th es e set s a r e

divided a mong t hree cla sses -

cen t in uou s, d is cr et e-r ea ct ion , a n d m ult ig rou p cr os s

sect ion s. NE S, t he num ber of energies a t w hich t he t ot al cross sect ion is t abula t ed,

a nd t he t emper at ure t o w hich t he cross sect ions w er e doppler broa dened a re given

for ea ch of t he t hree cla sses of cross-sect ion set s. C ompa rison of t he NE S va lues

gives one a n idea of how much det ail is provided in t he va rious cross-sect ion set s.

Under isotopic information t he na tura l a bunda nce for t he isot ope a nd t he densit y

3


16/292

va lue used in ca lcula t ing t he mea n free pa th q uot ed for ea ch pie-cha rt a re list ed;

t he sour ces of t hese da t a a re discussed in Appen dix A. Th e eva lua t ion in for ma t ion

denot es w het her or not t he eva lua t ion ha s phot on-pr oduct ion da ta a nd/or hea t in g

num bers a nd furt hermore, w het her t hese hea t ing numbers a re for loca l or t ot a l

hea t ing. This ma t t er is discussed in m ore det ail in sect ion I V. The energy ra nge of

t he ca lcula t ion is a lso list ed u nd er eva lua t ion in for ma t ion . Th e low er en er gy boun d

is 10-

5 eV for E ND F/B -V eva lua t ions a nd eva lua t ions fr om G r oup T-2. The low er

energy bound for E ND L-85 eva lua t ions is 10-

4 eV. G enera lly , t he upper energy

bound is 20 MeV; except ions a re duly not ed. U nder rea ct ion in form a tion a ll of

t he rea ct ions a nd t heir respect ive E ND F/B MT numbers a re list ed, a long w it h t he

r espect ive kin em a tic a n d r ea ct ion Q va lu es (d escr ibed in Appen dix A).

Th er e a r e a few is ot opes f or w h ich r ea ct ion s g iv en a s d is cr et e in ela s t ic s ca t t er in g

(51< MT < 90) ma y not be t ha t. I n order t o a ccura tely represent energy-a ngle

cor rela t ion of n eu tr on em is sion s pect r a f rom lig ht -elem en t r ea ct ion s, t h e cr os s s ec-

t ion is d ivided a m on g sever a l in ela st ic levels. I t is t his m et hod , som et im es r efer red

t o a s t he pseu do-level t ech niq ue, in w h ich d ist in ct ion bet w een kin em a tic QX a n d

rea ct ion QR becomes very import an t . There a re not es in Appendix B t o describe

t hese specia l ca ses a nd t o expla in t he repet it ion of t he sa me rea ct ion la bel in t he

f ir st col um n u nd er r ea ct ion in for m a t ion .

P ie-ch ar ts for ea ch eva lua t ion a re given a t 14 MeV, 1 MeV, a nd t her ma l en er gy .

At t hese en er gies t he per cen t con tr ibu tion of ea ch r ea ct ion t o t he t ot a l cr oss sect ion

is show n gr a ph ica lly a nd list ed num er ica lly , t he t ot a l cross sect ion in ba rn s a nd t he

mea n free pa th in cent imet ers a re list ed; t he form ula for t he mea n free pa th is

A

rnfp(cm) = x (lo24t@n2)

pNACTT

(1)

whe re

p

is t he den sit y (g/cm 3 ), A is t he a t om ic w eigh t (g/m ole), N A is Avoga r dos

num ber (= 6.023x1023 a tm/mole), a nd OT is t he t ot al cross sect ion in ba rns. The

TOTAL I NE LAS TI C cross sect ion , a ;., referred t o in t he pie cha rt s is t he sum of

t he cr os s sect ion s for in ela st ic-level sca t t er in g a n d t he cr os s sect ion for sca t t er in g

t o t he con tin uum ; viz,

90

Ui~ =

E

fT=i

n,n

+ (7:$=91

(2)

;=S1

The gra ph or plot da t a of t he cr oss sect ion s for t he va rious rea ct ions con sist of a

ser ies of in dividua l cur ves w hich ch ar act er ize t he rea ct ion s or E ND F/B MTs for a

g iv en n uclid e or is ot ope. Th ey a r e g rou ped in t o t h e follow i ng eig ht br oa d ca t eg or ies -

1. S um ma rv Rea ct ion s: The t ot a l, ela st ic, a bsorpt ion, a nd t ot a l fission r ea ct ion s;

t hese r ea ct ion s a r e a lw a ys defin ed over t he en tir e e~ er W r a nge. 2. H ea t in g Nu mber ;

The loca l or t ot il hea ting number in MeV/collision . 3. G a mma P roduct ion: The

t ot a l phot on-pr oduct ion cross sect ion . 4. F ission Rea ct ions: I n ca ses w her e t he t o-

t a l fission rea ct ion is given a s t he sum of rea ct ions (n, F )= (n ,f) + (n ,nf) + (n,2nf)

+ (n ,3nf), t he component rea ct ions a re given in t h is plot . 5. Nuba r D a ta The

prompt a nd t ot al U , t he a vera ge num ber of neut rons per fission , a re plot ted here.

Tot a l Z is la beled MT= 452; prompt D is MT= 456. I n ca ses w here t he Z could

4


17/292

be eit her prompt or t ot a l, it is ident ified by MT= 453. 6. Threshold Rea ct ions:

Th ese r ea ct ion s in clu de t ot a l in ela s tic sca t t er in ga n d a n ot h er n eg a t ive-Q r ea ct ion s

for which t here a re out going neut rons; for exa mple, (n ,2n), (n ,2na ), (n ,n p), a nd

(n ,4n ) r ea c t ion s .

7. Absor pt ion R ea ct ion s:

These a re t he component s of t he t o-

t a l a bsorpt ion rea ct ion , t hose rea ct ions for w hich no neut rons a re emit ted. One

ca n fin d h er e cr oss sect ion s for t he (n,p), (n,d), (n,3H e), (n ,a ), (n,2a ), (n ,2p), (n ,

pa ), a n d (n ,t 2cv) r ea ct ion s.

Rea ders should not e t ha t t he (n ,~ ) rea ct ion - a prin-

cipa l component of t he t ot a l a bsorpt ion cross sect ion rea ct ion - is not included

in t he foregoing list a nd is never individua lly plot t ed. This w as done in order

t ha t t he high-t hreshold a bsorpt ion rea ct ions could be clea rly seen on t his plot .

8. C h a r ge-P -a r t icle-P r od uct ion -R ea ct ion s: Th es e r ea ct ion s a r e r ed un da n t , w e re n ot

g iven in t he or igin a l eva lua t ion , a nd a r e n ot g iven in t he list of com pon en t r ea ct ion s

for t he eva lu at ion . Th ey a r e gen er a ted specia lly t o r epr esen t t he t ot a l cr oss sect ion

3H e, a nd o pa r ticles,

or pr od ucin g pr ot on s, d eu ter on s, t r it on s,

I t is import ant t o not e t ha t t he TOTAL INE LAS TI C cross sect ion MT= 4 plot -

t ed w it h t he t hreshold rea ct ions includes t he pa rt ia l cross sect ions for rea ct ions

b ein g r epr es en t ed u sin g t h e ps eu do-lev el t ech n iq u e.

Th e n uclide iden tifier n am e or ZAI D is a floa t in g poin t n um ber used t o iden tify

t he eva lua tion . E ach eva lua ted cross sect ion set ha s a unique ZAI D . The ZAID is

of t he form ZA.nnX. The port ion of t he ZAID t o t he left of t he decima l point is 2A,

w h er e, ZA= 1OOO*Z+ A a n d Z is t he ch a rge n um ber (a t om ic n um ber ) for t he elem en t

or isot ope a nd A is t he ma ss number. I f t he eva lua tion is for a mixt ure of isot opes,

A is set t o 0.0. For exa mple, 2A for t he element silicon is ZA= 14000. In t he ZAID ,

nn is

t he da ta set ident ifier a nd X indica tes one of severa l cla sses of da ta . H ence,

t he ZAI D for t he G roup T-2 eva lua t ion for deut er ium is 1002.55, w her e 2= 1, A= 2,

a nd nn= 55. For t hose cross-sect ion set s of concer n in t his Handbook, it is only

necessa ry t o dist inguish bet w een C la ss C , C la ss D , a nd Cla ss M (X= C ,D , a nd M)

da ta set s. C la ss C da ta set s a re cont inuous-energy cross sect ions in AC E forma t,

t he or igin al a nd t hinn ed cr oss sect ion s. The C la ss D da ta set s a re discr et e-

r ea ct ion cr oss sect ions in AC E for ma t . Th e C la ss M da ta set s a re m ult igr oup cr oss

sect ion s. F or t h e E N DF /B -V eva lu a t ion s,

nn is50

for t he or igina l a nd 51 for t he

t hinn ed cr oss sect ion s. Th e eva lua t ion s fr om G roup T-2 ha ve nn 55 or greater;

t he eva lua t ion s fr om E ND L-85 h a ve nn=35.

As a con ven ien ce t o t he user , t he elem en ts a re list ed a lph abet ica lly a ccor din g

t o na me in Ta ble I I , a nd in Ta ble I I I t he element s a re list ed a ccording t o a tomic

number. P lea se not e t ha t t he

Handbook

d oes n ot con t a in cr os s-s ect ion ev a lu a t ion s

for ever y elem en t in t he per iodic syst em (Ta ble I I).

III. ARRANGEMENT OF THE DATA

The da t a in t his volume ca n be considered in t erms of 3 modules; a t a bula r

da t a module, a pie-cha rt da t a module, a nd a gra ph or plot da t a module. E a ch of

t he modules cont ains 129 set s of da ta w hich ha ve been a ut oma tica lly forma tt ed

t o produce t wo pa ges of out put . The fir st pa ge cont ains t he t abula r a nd pie-cha rt

da ta a nd t he second pa ge cont ains t he gra phs or plot s.

5


18/292

A. Tabular Data

There a re 129 set s of t a bula r da ta cont a ined in t his volume, one for ea ch of

t he element s or isot opes on t he MC NP libra ry . The t abula r da ta module cont ains

releva nt expla na t ory inform at ion w hich w a s det a iled in t he previous sect ion. The

t abula r da ta or t ext ha s encoded T@Ccomma nds t o fa cilit at e t he forma tt ing of t he

pie cha rt s a nd t ext on a single pa ge.

B. Graphics Data

Th e H a ndbook con ta in s t w o gr a ph ics da t a m odu les, t he pie-ch a rt da t a m odule,

a nd t he gra ph or plot da ta module. The pie-cha rt module consist s of individua l

pie cha rt s w hich ha ve been genera t ed a t t hree differen t energies. Th e in dividua l

pie cha rt s a re t hen ordered a nd forma tt ed so a s t o be cent a ined in a single file a nd

subseq uent ly combined w it h t he t abula r da ta .

The gra ph or plot da ta module con sist s of a series of curves w hich cha ra ct er ize

t he r ea ct ions or E ND F/B MTs. These curves a re gr ouped int o va rious ca t egories

w hich for m a sin gle gra ph . F or ea ch gr aph t he cr oss sect ion in ba rns on t he ordina t e

is plot ted versus t he en ergy in MeV a lon g t he a bscissa . On t he upper r igh t ha nd side

of ea ch gra ph t he da te t he plot w as genera ted is given, follow ed by t he ZAID , t he

ch em ica l sy mbol for t he elem en t or isot ope, t he libr a ry u pon w hich t he eva lua t ion is

lis ted , a n d t h e M Ts bein g plot t ed . Th e gr a ph s of cu rv es a r e s ubseq uen tly for ma t t ed

so t ha t a ll ca t egories of curves a re cont a ined on a single pa ge. I t is under st ood t ha t

not a ll ca tegories of plot s a ppea r for every eva lua t ion. In fa ct , ea ch pa ge ma y

cont a in a s few a s t w o or a s ma ny a s six gra phs of plot s or curves.

IV. Heating Numbers

I ncluded a m on g t he plot s for ea ch ea ch n uclide (pa ge t w o of ea ch eva lu a tion ) is a

plot la beled H ea t ing Num bers in unit s of MeV/collision. On t he fir st pa ge under

eva lua t ion inform at ion t hese n umbers a re det a iled a s eit her loca l or t ot a l hea t ing

numbers. G enera lly, t he hea t ing numbers a re one of t he lea s~ derst ood items of

da ta a va ila ble t o t he user ; a s such, t hey m erit specia l a t t ent ion.

B y hea ting or hea ting numbers one is a ct ua lly referr ing t o t he loca l energy

deposit ion result ing from t he product ion of cha rged pa rt icle m ot ion by neut rons

a nd ga mma s. The hea t ing number is simply a mea ns of q ua nt izing or ca lcula t ing

t his effect . The hea ting number H (E ) is a funct ion of incident neut ron energy E ,

a nd is a mea sure of t he energy deposit ed per collision. In loca l hea t ing t he energy

of t he seconda ry neut rons a nd phot ons is a ssumed to be ca rr ied a w a y from t he

sit e of t he rea ct ion. Loca l neut ron hea t ing is t herefore due t o t he kinet ic energy

of t he recoil nucleus, of t he emit ted ch arged pa rt icles, a nd of t he ch ar ged pa rt icles

produced by ra dioa ct ive deca y of t he residua l nucleus. Tot al neut ron hea t ing is

t he sum of t he energy ca rr ied a wa y by t he phot ons a nd t he energy deposit ed in

t he collision . Ot her processes such a s int er na l con ver sion a lso cont ribut e t o loca l

6


19/292

neut ron hea t in g. F or a det a iled expla na t ion of t his ph en om enon, plea se see Ref. 12

(pa ge 5) a nd 13 (pa ge 91).

I n h is d es cr ipt ion

14 of t he H EATR module in NJ OY, McF a rla ne poin t ed out

t ha t t he hea ting number could be ca lcula ted in a forw a rd w ay using K E RMA15

fa ct ors (K inet ic E nergy ~ elea sed in I &eria l). I n t he energy densit y t erms used by

NJ OY of eV/cm3, t he hea ting ra te in a ma ter ia l is,

xx

~i~ij(~)+(~)

i

3

interactions reactions

(3)

w here E is t he incident energy , n i is t he a tot ic densit y of ma teria l i, @(E ) is t he

sca la r flux of eit her neut rons or ga mma s, a nd k is t he K errna fa ct or a nd is in eV-

ba r ns. Th e ker ma fa ct or is obt a in ed by m ult iply in g ea ch in ter a ct ion cr oss-sect ion

by t he loca lly d eposit ed en er gy pr od uced , t hus:

(4)

w her e t he sum is over t he 1 species of ch a rged pa r ticles pr od uced , in clu din g r ecoil,

in t he int era ct ion j, on t he ma t~ r ia l i, a t t he incident neut ron energy E , producing

t he m ea n energy per collision, E ijt . MC NP needs

(5)

a s t he hea ting number. U nfor t una tely, E ND F/B eva lua tions do not include t he

d et a iled s pect ra l in for ma t ion n eed ed t o ca lcu la t e E ijl.

The a lt erna t ive a pproa ch w hich is used in NJ O Y t o cilcula te t he hea t ing num-

ber s is t he en er gy ba la n ce m et hod .

The en er gy ca rr ied a w a y by t he neut rons a nd

phot ons is subt ra ct ed fr om t he t ot a l ener gy a va ila ble; t he r em ainder is a ssumed t o

be t he ch arged-pa rt icle a nd r ecoil ener gy , a ll of w hich is loca lly deposit ed. H ence

t he kerma fa ct or is:

kij(E) = (E + Qij Aij.(E) f i i j7(~))~:j(~)

(6)

a n d t he h ea t in g n um ber is eff ect ively k i j /a i j w h er e Qi~ is t he Q-Va lue (m a ss d iffer -

ence) for rea ct ion i on t he t a rget j,

& i j n

is t he m ea n out goin g neut ron en ergy , a nd

& i j 7

is t he m ea n out goin g ga mm a en ergy . Th us,

(7)

E q ua t ion (7) w h ile t h eor et ica lly cor rect is of lit t le pr a ct icz d v a lu e, s in ce ph ot on -

pr odu ct ion in for ma t ion is n ot a va ila ble on a r ea ct ion -by -r ea ct ion ba sis. I nst ea d t he

ker ma s a r e r ed efin ed v iz :

7


20/292

(8)

~Uij(E)

j

The t ot a l hea ting number includes t he energies of a ll phot ons produ~ , t he

loca l h ea t in g n um ber ha s t he ph ot on en er gies r em oved. Th e dist in ct ion bet w een

j a nd jt is significa nt .

The cr oss sect ions for t he j~ phot on product ion rea ct ions

a re independent of t he j neut ron rea ct ions. I n ca lcula ting H ~ l(E ) one ta kes t he

d iffer en ce bet w een t w o la r ge n um ber s.

E xt reme ca re must be t a ken in t he ca l-

cula tion of k~ (l?) a nd k~,(E) but - more import a nt ly - ext reme ca re is needed

in t he prepa ra tion of t he eva lua ted da ta t o insure tha t proper energy ba la nce is

ma int ained. When ener gy ba la nce is considered a ppropria t ely, t he loca l hea t ing

n um ber s H ~ t i ~ (E ) w ill be pos it ive.

An a lt erna tive a nd somew ha t simpler depict ion of t he hea ting number is t he

differ en ce ca lcula t ion em ployed by C a rt er a nd C a shw ell (Ref. 13). I n t his ca a e

H=lJ+~--Et-rt

(9)

w here E is t he incident neut ron energy , ~ is t he a vera ge Q-Va lue, E is t he average

energy of t he seconda ry neut rons, a nd 17 is t he a vera ge energy of t he

outgoing

photons.

The difference (E + ~ )-(E + 1) is t he cha rged pa rt icle hea t ing assumed to be

d eposit ed w it hin a n egligible dist a nce fr om t he r ea ct ion (h en ce t he t er m loca l neu-

t ron hea t ing). The a ssum pt ion is t ha t neut ron s a nd phot ons esca pe t he

immediate

v olu me a n d d eposit t heir en er gy elsew h er e.

E qua t ion (9) a ga in rein forces t he fa ct t ha t t he incorrect ca lcula t ion of P will

result in nega t ive hea t ing numbers. I n t he pa st t his problem ha s been pa rt icula rly

t roublesome a s illust ra ted in t he w ork of S ora n a nd S ea men (Ref. 12) w here 26 of

t he 68 eva lua tions on t he RMC C S libra ry a t t ha t t ime ha d nega tive loca l hea ting

numbers. C ompa re t ha t w it h t he present MC NP libra ry w hich ha s 28 of t he 129

eva lua t ions w it h a t lea st on e nega t ive loca l hea t ing num ber; t hose eva lua t ions a re

list ed in Ta ble V. Tw o fa ct ors essent ia l in t he improvem ent of t he hea t ing num ber

ca lcula t ion a re a ) bet ter energy ba la nce considera t ions a nd b) significa nt ly im-

pr oved eva lua t ion s a nd eva lua t ion al m et hods. I nciden ta lly , t he Mon te C a rlo code

8


21/292

MC NP does not use nega tive hea ting numbers but set s t hem t o 0.0 w hen t hey a re

encountered.

V. DISCUSSION

Th is pu blica t ion of t he C ross S ect ion D a ta H a ndbook is pa r ticu la r ly sign ifica n t

bot h for it s cont ent s a nd t he met hodology used t o genera te, order, a nd a ssimila te

t he cont ent s. This ma rks t he first t ime t ha t t he t abula r a nd gra phic da ta for a ll nu-

clides on t he MC NP D efa ult C ross S ect ion Libr ar y h ave been con ta ined in t he sa me

volu me. Th e t a bula r da t a in clud es t he or ig in of t he con tin uou s en er gy eva lua t ion ,

i.e., (t he eva lua t or (s) a nd t he r efer en ce in w h ich t ha t eva lua t ion w a s publish ed ),

a

list

of a ll cur ren tly a va ila ble da ta for a given n uclide, I sot opic I nfor ma t ion, E va l-

ua t i on I nfor ma t ion (ph ot on -pr od uct ion , h ea t in g, et c.), a nd R ea ct ion I nfor ma t ion

(MT n um ber s, en er gy r a ng e, a n d Q-Va lu es).

The first st ep in det ermining a met hod t o t he ordering a nd smimila tion of t his

t remen dous a mount of ma t er ia l w a s t o decide upon t he eva lua tion s t o be in cluded

a nd t heir forma t. I t w as decided a lmost immedia tely t ha t ea ch ma teria l or nuclide

w ould not ha ve more t ha n t w o pa ges of t a bula r da ta a nd/or plot s or curves (t o do

ot h er w ise w ou ld m a ke t h e pu blica t ion t oo volu min ou s, t h us d efea t in g it s pu rpose).

The second st ep w a s t o enumera t e a nd a ut oma t e ea ch t a sk w hich ha d t o be

per for med t o effect t he gen er at ion, a nd a ssim ila t ion of t he h ea ding, gr aph ic, a nd

t a bula r da ta for ea ch nuclide. In it s fina l form t he forw ard pa ge of da t a for ea ch

n uclid e in clu des a ll of t h e in for ma t ion a llu ded t o a bove plu s cr oss-sect ion in for ma -

t ion in t he for m of pie-ch ar ts a t 14 MeV, 1 MeV, a nd 2.53E -08 MeV. Th e ba ck pa ge

in clu des cr os s-s ect ion plot s or cu rv es exclu si vely . Th es e plot s h a ve been g rou ped or

ca tegorized a nd a re commonly r eferred t o a s t he S umma ry Rea ct ions (MTs 1, 2,

101, 18); H ea t ing Da ta (MT= 301); G amma P roduct ion D at a (MT= 302); Thresh-

old Rea ct ions (MTs 4, 16, 17, 22, 24, 25, 28, 37); Fission Rea ct ions (MTs 19,

20, 21, 38); Absor pt ion Rea ct ions (MTs 103, 104, 105, 106, 107, 108, 111, 112,

113); a nd Tot al P r ot on P r oduct ion, Tot al D eut er ium P roduct ion , Tot a l Tr it ium

P r oduct ion, Tot a l 3H e P roduct ion , a nd Tot aJ 4H e P roduct ion (MTs 203, 204, 205

206, 207, a nd 208). P lea se see Ta ble I V for a complet e list of t he Rea ct ion Types

or MT n um ber s a nd t heir sign ifica n ce.

The a ccomplish men t of t he secon d st ep w a s a ver y lon g, t ime-consum in g, a nd

exa ct ing process w hich required numerous cha nges bot h t o t he genera tion code

XD ATAP 16 w h kh g en er a t ed t h e G r a ph ic D a t a (pie-ch a rt s a n d cr os s s ect ion cu rves ),

a nd t o t he F or tra n C om ma nd La ngua ge (F CL17 ) pr ogr am w hich w a s t he m achiner y

used t o a ut oma te a ll of t he processes.

Furt hermore, a w a y ha d t o be devised t o

a ut oma tica lly couple t he out put of t he FC L progra m on t he C TS S syst em t o t he

&jX forma tt ing progra m on t he U NIX syst em w hich t ra nsla ted a nd forma tt ed t he

FC L out put , t he hea ding a nd t a bula r da t a , a nd produced t he pa ges w hich a re

con ta ined in t his volum e. To a ccom plish t he la t ter t ask, a sma ll C SH E LL pr ogr am

ca lled MKH B K w as w rit ten w hich ext ra ct ed a ll of t he required informa tion from

t he C TS S syst em, a ut oma tica lly ra n it t hrough t he t ext forma tt ing progra m, a nd

produced t wo ha rd copies for ea ch eva lua tion. U ndernea th t he a ct ivit y of t he t wo

ma jor progra ms ment ioned a bove, a myria d of t a sks ha d t o be performed t o ma ke

9


22/292

t he fut ure genera t ion of t his document a s a ut oma tic a s t he preva iling com put er

syst ems w ould a llow . Included a mong t hese t asks (a ll of w hich fa ll under t he F CL

um brella ) is a rout ine ca lled G NRATE w hkh a ut oma tica lly genera tes a nd st ores

t he pie-ch a rt s a n d cr oss-sect ion cu rves for a n y eva lua t ion on t he MC NP libr a ry fr om

a n input file; t he MAK E r out in e, w hich a ut om at ica lly fet ch es t he da ta pr oduced by

t he G NRATE rout ine for a n eva lua t ion, enumera tes t he number of plot s, forma ts

t he hea ding da ta or t ext , t he pie-cha rt s, a nd t he cross-sect ion curves, a nd st ores

a ll of t his da ta in t he a ppropr ia te direct ories w here it is ret rieved by t he C SH ELL

program.

The poin t t o empha size here is t ha t a lt hough t he genera t ion of t his document

t ook a grea t dea l of t ime, it is a t a sk t ha t w ill on ly ha ve t o be per formed once;

t ha t is t o sa y t ha t t he t a sk of producing t h is or simila r volumes ha s been a lmost

com plet ely a u t om a t ed ; con seq u en t ly , t h e u pd a t e of a s in gle n u cl id e, s ev er a l n ucli des ,

or t he en tir e volu me ca n be r ea d ily a ccom plish ed.

I

)

10


23/292

REFERENCES

1,

2,

3.

4.

5.

6.

7.

8.

9.

10.

J . F . B riesmeist er , edit or , MC NP -A G enera l Mont e C a rlo C ode for Neut ron

a nd P hot on Thnsport , Version 3A, Los Ala mos Na tiona l La bora tory ma nua l

L A-7396-M , R ev . 2 (S ept em ber 1986).

R . K in sey , com piler , E ND F/B S umma ry D ocument at ion , B rookha ven Na -

t ion a l L a bor a t or y r epor t B N L-N CS -17541 (E N DF -201) 3r d ed it ion (E N DF /B -

V) (J uly 1979).

B . A. Ma gurno a nd P . G . Young, edit ors,

EN DF -201 S upplem en t I E N DF /B

V.2 S um ma ry D ocument a tion,

B rookha ven Na tiona l La bora tory repor t

B NL-NC S-17541 (E ND F-201) 3rd E dit ion (E ND F/B -V) S upplement I (J a n -

U V 1985).

R. J , H ow er t on a nd M. H . Ma cG regor , The LLL E va lua t ed Nuclea r Da ta

Libra ry (E ND L): D escr ipt ion of I ndividua l E va lua t ions for 2= 0-98, L aw ren ce

Livermore La bora tory repor t U CRL-50400, Vol. 15, P a rt D , Rev. 1 (Ma y 17,

1978).

R. D . OD ell a nd F. W. B rinkley , J r., a nd D. R. Ma rr U ser s Ma nua l

for ON E DAN T: A C od e P a cka g e f or O ne-D im en sion a l, D iffu sion -Acceler a t ed ,

N eu tr a l-P a r t icle Tr a ns por t , L os Ala m os N a tion a l L a bor a t or y m a nu a l L A-9184-

M (F ebr ua r y 1982).

R. E . Alcouffe, F . W. B r inkley , J r ., D . R. Ma rr , a nd R. D . OD ell,

U ser s G uide for TWOD ANT: A C ode P acka ge for Tw o-D imensiona l,

D iffu sion -Acceler a t ed , N eu tr a l-P a r t icle Tr a nspor t, L os Ala m os N a tion a l L a b-

or a t or y m a nu a l L A-1 OO49-M, R ev. (Oct ober 1984).

R. C . Lit t le, R. E . S ea men, a nd P . D . S ora n, Rea ding t he C RAY F ile ME ND F -

5, Los Ala rnos Na tiona l La bora tory in t erna l memora ndum t o F. W. B rinkley

(M a r ch 15, 1983).

R. C . Lit tle, Mult igroup C ross-S ect ion Ta bles for MC NP 3B (Revised), Los

Ah un os Na t ion a l L a bor a tor y in ter na l m em or a nd um X-6: R CL -87-161 t o D ist ri-

bu tion (M a rch 11, 1987).

R. E . Ma cFa rla ne, D . W. Muir , a nd R. M. B oicourt , The NJ OY Nuclea r D a ta

P rocessing S yst em, Vol. I : U ser s Ma nua l: Los Ala rnos Na tiona l La bora tory

m a nu al L A-9303-M, Vol. I (E ND F-324) (M a y 1982).

H . M. Fisher , P repa ra tion of t he E ND L-85 C ross S ect ion Libra ry in AC E

Forma t, Los Ala mos Na tiona l La bora tory int erna l memora ndum X-6:H MF -

86-261 t o R. C . Lit t le a nd R. E . S ea rnon (J u ne 23, 1986).

\

\

11


24/292

11. R. J . H ow ert on , R. E . D ye,P . C . G iles, J . R . K ir nlinger , S . T. P erkins, a nd E .

F . P lech a ty ,

OME G A: A C RAY 1 E xecut ive C ode for LLNL Nuclea r D a t a

L ibr a ries, L aw r en ce L iver mor e N at ion a l L abor a tor y r epor t U C RL -50400 Vol.

25 (Au gu st 1983).

12. P . D . S ora n a nd R. E . S ea m en,

G ra phs of t he C ross S ect ions in t he Recom -

m en ded Mon te C a rlo C ross-S ect ion Libr ar y a t t he Los Ala mos S cien tific La b&

r at or y, LA R epor t 8374-MS (Ma y 1980).

13. L. L. C a rt er , a nd E . D . C a shw ell, P ar t icle-Tra nsport S im ula tion w it h t he

Mon te C a rlo Met hod , E RD A C rit ica l R eview S er ies TI D-26607 (1975).

14. R. E . Ma cF a rla ne, D . W. Muir , a nd R. M. B oicourt , The NJ OY Nuclea r D a ta

P rocessing S yst em, Volum e I I: The NJ O Y, RE CONR, B ROAD R, H EATR, a nd

TH E RMR Mod ules, Los Ala m os Na t ion a l L abor a tor y m a nua l L A-9303-M, Vol.

I I (E N DF -324) (M a y 1982).

15. M. A. Abdou, C . W. Ma yna rd, a nd R. Q. Wright , MAC K : A C om put er P ro-

gr a m t o C a lcu la t e Neu tr on E n er gy R elea se P a r a met er s (F lu en ce-t o-K er ma F a c-

t or s) a nd Mult igr oup Rea ct ion C ross S ect ion s fr om Nuclea r D at a in E ND F F or -

m at , Oa k Ridge Na t ion al La bor at or y r epor t ORNL-TM-3994 (J u ly 1973).

16. H . M. F ish er , XD ATAP , LA-11155-MS , (Oct ober 1987).

17. FC L~ Los Ala mos Na tiona l La bora tory C omput er a nd C omm unica tions D i-

vision C IC l 114 (Au gu st 1987).

18. R. C . Wea st , C RC H a ndbook of C hem ist ry a nd P hysics 69TH E dit ion , C RC

Pres s Inc. , 1988-1989.

19. J . J . D eva ney, D en sit ies of Tr an sur an ic I sot opes, Los Ala rn os Na t ion al La b~

r a t or y in ter na l m em or a nd um X-6: J J D -88-132 t o H . M. F ish er (Ma r ch 17, 1988).

20. J . J . D eva n ey , N ept un iu m D en sit ies,

L os Ala m os N a t ion a l L a bor a t or y in t er n a l

memora ndum t o H . M. Fisher (J u ne 16, 1988).

21. F. W. Wa lker , D . G . Miller , a nd F. Feiner , edit or s, C ha rt of t he Nuclides,

13t h ed it ion G e ner a l E lect r ic C om pa n y (1984).

12


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TAB LE I . List of E lement s a nd Isotopes Cont ained In This Volume

M ate r ia l

ZAID

H

D

T

He-3

He-4

Li-6

Li-7

Be-7

Be-9

B -10

B -n

c

C-12

C-13

N-14

N-15

0-16

F-19

Na-23

Mg

Al-27

S i

P -31

S-32

cl

Ar

K

C a

Ti

v

C r

Mn-55

Fe

co-59

Ni

Ni-58

C u

G a

As-74

As-75

Kr-78

Kr-80

Kr-82

1001.5OC

1002.55C

1003.5OC

2003.50C

2o04.5oc

3006.50C

3007.55C

4007.35C

4009050C

501.5OC

5011.56C

6000.50C

6012.50C

6013.35C

7014.50C

7015.55C

8016.50C

9019.50C

11023.5OC

12000.50C

13027.50C

14000.50C

15031.50C

16032.50C

17000.50C

18000.35C

19000.50C

20000.50C

22000.50C

23000.50C

24000.50C

25055.50C

26000.55C

27059.50C

28000.5oc

28058.35C

29000.50C

31OOO.5OC

33074.35C

33075.35C

36078.50C

36080.50C

36082.50C

M ate r ia l

Kr-83

I


26/292

TAB LE I I.

L ist of E lem en ts Alph a bet ica lly Accor din g t o N am e

Actinium

Aluminum

Americium

Antimony

Argon

Arsenic

Astatine

B a r i u m

Berkelium

Beryll ium

Bis muth

Boron

Bromine

Cadmium

Calcium

Californium

Carbon

Cerium

Cesium

Chlorine

Chromium

Cobalt

Copper

Curium

Dysprosium

Einsteinium

Erbium

Europium

Fermium

Fluorine

Fhncium

Gadolinium

Gall ium

Germanium

Gold

A c 89

Al 13

Am 95

S b 51

Ar 18

As 33

At 85

B a 56

B k 97

B e 4

B i 83

B 5

B r 35

C d 48

C a 20

C f 98

C 6

C e 58

C s 55

cl 17

C r 24

C o 27

C u 29

C m 96

D y 66

E s 99

E r 68

E u 63

Fm 100

F9

F r 87

G d 64

G a 31

G e 32

Au 79

Hafnium

Hahnium

Helium

Holmium

Hydrogen

Iodine

Iridium

Iridium

Iron

Krypton

Kurchatovium

L a n t h a n u m

Lawrencium

Lead

Lithium

Lutetium

Magnesium

Manganese

Mendelevium

Mercury

Molybdenum

Neodymium

Neon

Neptunium

Nickel

Niobium

Nitrogen

Nobelium

Osmium

Oxygen

Pa l ladium

Phosphorus

Pla t inum

Plutonium

Polonium

H f 72

H a 105

H e 2

H o 67

H I

I

53

I n 49

I r 77

Fe 26

K r 36

Ku 104

La 57

Lw 103

P b 82

Li 3

Lu 71

Mg 12

Mn 25

Md

101

H g 80

MO

42

Nd 60

Ne 10

Np 93

Ni 28

Nb 41

N7

No 102

@ 76

08

P d 46

P

15

P t 78

P u 94

P o 84

P o t a s s iu m

Praesodymium

Promethium

Protactinium

Radium

Radon

Rhenium

Rhodium

Rubidium

Rutheniun

S amarium

Scandium

Selenium

Silicon

Silver

Sodium

Strontium

Sulfur

Tantalum

Technetium

Tellurium

Terbium

Thallium

Thorium

Thulium

Tin

Titanium

Tungsten

U r a n i u m

Vanaclium

Xenon

Ytterbium

Yttrium

Zinc

Zirconium

K 19

P r 59

P m 61

P a 91

Ra 88

Rn 86

Re 75

RI-l 45

Rb 37

Ru 44

S m 62

S c 21

S e 34

S i 14

Ag 47

Na 11

S r 38

s

16

Ta 73

Tc 43

Te 52

Tb 65

T1 81

Th 90

Tm 69

S n 50

Ti 22

w 74

u

92

v 23

Xe 54

Yb 70

Y

39

Zn 30

Zr 40

14


27/292

T.4B L E H I .

List of E lem ent s Accor din g t o At om ic Num ber

Symbol

Name

Symbol

Name

Symbol

Name

lH

2 H e

3 Li

4 B e

5B

6C

7N

80

9F

10 Ne

11 Na

12 Mg

13 Al

14 S i

15 P

16 S

17 cl

18 Ar

19 K

20 C a

21 S c

22 Ti

23 V

24 C r

25 Mn

26 Fe

27 C o

28 Ni

29 C u

30 Zn

31 G a

32 G e

33 As

34 S e

35 B r

15

Hydrogen

Helium

Lithium

Beryll ium

Boron

Carbon

Nitrogen

Oxygen

Fluorine

Neon

Sodium

Magnesium

Aluminum

Silicon

Phosphorus

Sulfur

Chlorine

Argon

P o t a s s iu m

Calcium

Scandium

Tit anium

Vanadium

Chromium

Manganese

Iron

Cobalt

Nickel

Copper

Zinc

Gall ium

Germanium

Arsenic

Selenium

Bromine

36 Kr

37 Rb

38 S r

39 Y

40 Zr

41 Nb

42 Mo

43 Tc

44 Ru

45 Rh

46 P d

47 Ag

48 C d

49 In

50 S n

51 S b

52 Te

53 I

54 Xe

55 C s

56 B a

57 La

58 C e

59 P r

60 Nd

61 P m

62 S ln

63 E u

64 G cl

65 Tb

66 D y

67 H o

68 E s

6 3 Tm

70 Yb

Krypton

Rubidium

Strontium

Yttrium

Zirconium

Niobium

Molybdenum

Technetium

Ruthenium

Rhodium

Pa. l lachurn

Silver

Cadmium

Iridium

Tin

Antimony

Tellurium

Iodine

Xenon

Cesium

B a r i u m

L anthanum

Cerium

Praseodymium

Neoclymium

Promethium

S amarium

Europium

Gaclolinium

Terbium

Dysprosium

Hohnium

Erbium

Thulium

Ytterbium

71 Lu

72 H f

73 Ta

74 w

75 Re

76 0s

77 I r

78 P t

79 Au

80 H g

81 T1

82 P b

83 B i

84 po

85 At

86 Rn

87 Fr

88 Ra

89 Ac

90 Th

91 P a

92 u

33 Np

94 P u

95 Am

96 C m

97 B k

98 C f

9 3 E s

100 F m

101 l Id

102 N o

103 L r

104 K u

105 H a

Lutetium

Hafnium

Tantalum

Tungsten

Rhenium

Osmium

Iridium

Pla t ium

Gold

Mercury

Thallium

Lead

Bis muth

Polonium

Astatine

Radon

Francium

Radium

Actinium

Thorium

Protactinium

Uranium

Neptunium

Plutonium

Americium

Curium

Berkelium

Californium

Einsteinium

Fermium

Mendelevium

Nobelium

Lawrencium

Kurchatoviurn

Hahnium


28/292

TAB L E I V.

L ist of Rea ct ion Types or MTs

MT

1

2

4

16

17

18

19

20

21

22

24

25

28

37

38

51

52

.

.

90

91

101

102

103

104

105

106

107

108

111

112

203

204

205

206

207

301

302

452

456

16

M icr os cop ic C r os s -S e ct i on R ea c t ion

Total

E l a st ic s ca t t er in g

Tot a l in ela s t ic s ca t t er in g

(n,2n)

(n,3n)

Tota l f iss ion

(n ,f ) (f ir st ch a n ce f is sion )

(n ,n f ) (s econ d ch a n ce f is si on )

(n ,2n f) (t hir d &m ce fis sion )

(n,na)

(n,2ncu)

(n,3ncr)

(n,np)

(n,4n)

(n ,3n f ) (f ou r th ch a n ce f is si on )

(n ,n ) t o first excit ed st at e

(n ,n ) t o secon d excit ed st a te

.

.

~ n , n) t o 40t ~ e xcit ed st a t e

(n ,n ) t o con t in uu m

Absorption

(n ,y ) r a dia t iv e ca pt ur e

(n,p)

(n,d)

(n,t)

(n,3He)

(n,a)

( n ,~~)

(n,2p)

(n,pa)

Tot a l pr ot on pr od uct ion

Tot a l d eu t er iu m p rod u ct i on

Tot a l t r it iu m pr od uct ion

Tot a l 3H e p rod u ct i on

Tot a l 4H e p rod u ct i on

H ea t in g da t a

G a m m a pr od uct ion

Tot a l n uba r

P r om pt nuba r


29/292

TAB L E V, E va lua t ion s Wit h Nega t ive H ea t in g Num ber s

M ate r ia l

ZAID

E lem en t Na m e

F-19

Mg

Al-27

S i

P -31

Ti

v

C r

Mn-55

co-59

Ni

Ni-58

C u

Nb-93

Mo

FP -AVG

Ba-138

Eu-151

G d

Ho-165

Ta -181

P t

W-183

W-184

Au-197

P b

B i-209

Th-232

9019.50C

12000.50C

13027.50C

14000.50C

15031.50C

22000.50C

23000.50C

2400050C

25055.50C

27059.50C

28000.50C

28058.35C

29000.50C

41093.5OC

42000.50C

50120.35C

56138.50C

63151.55C

64000.35C

67165.55C

73181.50C

78000.35C

74183.55C

74184.55C

79197.56C

82000.50C

83209.5oc

90232.5oc

Fluorine

Magnesium

Aluminum

Silicon

Phosporus

Titanium

Vanadium

Chromium

M ang ane se

Cobalt

Nickel

Nickel

Copper

Niobium

Molybdenum

Av er a g e F is sion P r od uct

B a r i u m

Europium

Gadolinium

Holmium

Tantalum

Pla t inum

Tungsten

Tungsten

Gold

Lead

Bismuth

Thorium

Library

ENDF5P3

ENDF5U3

R M C C S

ENDF5P3

ENDF5U3

ENDF5U2

ENDF5U2

R M C C S

ENDF5U3

ENDF5U3

R M C C S

ENDL853

R M C C S

ENDF5P3

ENDF5U2

ENDL853

RMCCS

NEWXS3

RMCCSA

NEWXS3

ENDF5U2

RMCCSA

RMCCSA

RMCCSA

NEWXS3

RMCCS

ENDF5U2

ENDF5U3

17


30/292

Reaction

e la a t i c

(n,-f)

Hydrogen-1

ZAID = 1OO1.5OC

S O U R C E : E N D F /B -V (M AT= 1301,

R E F E R E NC E : S um m a r y D ocu m en t a l

by L. S tew a rt , R. J . La B auve, a nd P .

conta ine d in ENDF201

D a t a A

vailabil i t .~

C on t in uou s E n er gy

ZAID= 1OO1.5OC

NE S = 244 T= 300W

ZAID = 1OO1.51C

NE S = 244 T= 30&K

ZAID = 1OO1.53C

NE S = 394 T= 60C FK

D i scr et e R ea ct i on

ZAID= 1OO1.5OD

NES=263

T= 300J K

Multigroup

Z AI D = 1 OO 1 . 5o M

3&G roup T= 30&K

Jsotowe Informat

,io~

Abundance.99.985%

D en si ty = 8 .99E 05 g m/cm 3

E v a lu a t ion I n for m a t ion

P hot on-P roduct ion D at a Yes

H ea tin g Num ber s L oca l

E n ergy Ra nge 10-11 t o 20 MeV

Reaction Infomatbu

MT

Ihi . (hhv)

&..(Mev) Q~ c(Mev) QR(Mev)

2 1.0000-11 2. 0000+ 01

102

1.0000-11

2. 0000+01 2. 2246+00 2. 2246+00

Ta pe 511)

: ion f or 1H w

.. .

$3

m

%Xx%%

grr~

i%d

4

?. .....

Id

aiD-Mooomc

d

t

Wd

Id

NW- W (M@

aw~

n- Nu

m8 m NDnus

m -m

Molwmoo

MT-m

mlJTcNuu

n

UT-SOS

rNnuMMO D

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

n -m

Hx- s mm

m-m

AUWA m oo

9


88/292

Vanadium

ZAID=23000.50C

SOURCE:NDF/B-VMAT=1323,ape 508)

R E F E R E N C E : F a st N eu t r on C r os s S ect i on s of Va n a d i um a n d a n E v a l ua t e d N eu t r on ic F il e,

by P . G u en th er , D . H a vel, R . H ow er ton , F . Ma n n, D . S mit h, A. S mit h, a n d J . Wh a len

conta ined in ENDF201

~


ZAID = 23000.50C

NES= 2265

T.3WK

ZAID = 23000.51C

NES= 1899

T= 30@K

D ~ c r e t e R e a ct i on

ZAID = 23000.50D

NES= 2 6 3

T= 300K

ZAID= 2WO0.51D

NES= 2 6 3

T=30@K

Multigroup

ZAID= 23000.50M

30-Group

T= 30&K

Abundanc e= Natura l

D endty= 5 . 96 0 gm/c m3

Evaluat

i on I n f or ma t i on

P hot on-P roduct ion D ata - Yea

H ea tin g Num ber e - Loca l

E nergy Ra n ge -10-11 t o 20 MeV

~

Rea ct ion MT E mi.(MeV) E ~ ..[MeV)

Q~ (MeV) QR(MeV)

e la e tk

(n , am)

(n,n )a

(n,n)p

(n,rl1)

(n,na)

(n,ns)

(n,n4)

(Il,m s)

(n,n6)

(ll,n? )

(ll,m c)

(n , ? )

(Il,p)

(n,d)

(Il,t)

(n,a)

2

;:

28

61

52

63

54

65

56

67

1:;

103

104

106

107

1.0000-11

1. 1271+ 01

1. 0 49 7+ 01

8.2114+ 00

3.2644-01

9.4739-01

1 . 64 10+ 00

1 . 84 90+ 00

2 . 4 56 7+ 00

2 . 7 28 0+ 00

3. 1410+ 00

:. :Xl :;

1: oooo~ l 1

6. 9424+ 00

1 . 0 72 6+ 01

1.0000-11

2

2.

2.

2.

2.

i:

::

2.

::

2.

2.

2.

2.

0000+ 01

0000+ 01

0000+ 01

0000+ 01

0000+ 01

0000+ 01

0000+ 01

0000+ 01

0000+ 01

0000+ 01

0000+ 01

0000+ 01

0000+ 01

0000+ 01

0000+ 01

0000+ 01

0000+ 01

-1.

-1.

-8.

3:

-1 .

:: :

-2.

-3.

-; .

.

-::

-1.

7.

-.

.,

10s2+ 01

0293+ 01

0520+ 00

2010-01

2900-01

6090+ 00

8130+ 00

4090+ 00

6750+ 00

0800+ 00

9421+ 00

3040+ 00

0000+ 00

8270+ 00

0618+ 01

5900-01

-1. 1052+ 01

-1. 0293+ 01

-8. 0620+ 00

o. 0000+ 00

o. 0000+ 00

0 . 0 00 0+ 00

o. 0000+ 00

o. 0000+ 00

o. 0 000+ 00

o. 000 0+ 0 0

-2. 9421+ 00

7. 3 04 0+ 00

3.0000+ 00

-6 . 82 70+ 00

-1.0518+ 01

7.6900-01

lWERKAL

Srclvr -10.12 barna

MFF-1.4oum

E= f~hV

SIcswr = 2.61 barns

xl?P=6.65cm

E=14MAW

Slcnn

-s . ssbnnu

wP-6.3oem

76


89/292

23000.50C

Kiil

77

w-i

IV 8

..._

lr-fol

Wo.

aamosmc

V hw

xAiDssnw vc

v-m

$AID8aouvmc

v-m

h swwmm

mr-

-

Mm.mu

iliz

D

xAms800vJm

v-w

R9m~

%Gwl lnD

&t%mG

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

u-m

Alwu-

9


90/292

Chromium

ZAID=24000.50C

SOURCE: ENDF/B-V (MAT= 1324, Tape 512)

REFERENCE: Summary Documentation Natural Cbromium Evaluation EN DF/BV MAT= 1324,

by A. Prince and T. W. BurI

contained in ENDF-201

Continuous Energy

ZA1D=24000.50C NES=1105O T=300K

ZAID=24000,51C NES=1927

T=300K

Discrete Reaction

ZAID=24000.50D

NES=263

T=300K

Multigroup

ZAID=24000.50M 30-Group

T=300K

Js

oto~e I

nformation

Abundance= Natural

Density=7,20 grn/cm$

Evaluation Infor

matio~

Photon-Production Data Yes

Heating Numbers Local

Energy Range -10-11 to 20

Me V

Reac t ion Info

rmation

MT E~in(MeV) E~~=(MeV)

QK (MeV)

%(Mev)

,0000+ 01

0000+ 01 -7,

2.0000+ 01 -14

2. 0000+ 01 -7,

2. 0000+ 01 -9,

2. 0000+ 01 -5,

2. 0000+ 01 -7.

rows

THERMAL

.91mtn - 7.w bnrna

W$P.lmcm

Reaction

elaet ic

(n,2n)

(n,$n)

(n,n )a

{z ::

(n,n2)

(n,nS)

(n,a4)

(n,n5)

(n,n6)

(n,n7)

(m ,n$)

(n,n9)

(n,n10)

(n,n11)

(n,n12)

(n,n13)

(n,n14)

(n,n15)

(n,n16)

(Ia,n l?)

(n,nlS)

(n,n19)

(n,n20)

(n,n21)

(n,n22)

(n,n23)

(n,n24)

(n,n25)

(n,n26)

(n,n27)

(n,n2S)

(n,n29)

(Il,nso)

(n,nSl)

(Il$nsa)

(n,n33)

(n,n34)

(n,nS5)

(n,nS6)

(n,nS7)

(n,nS8)

(n,n39)

(n,n40)

~; )

(n,p)

[:::)

(n,He)

(n,a)

0000- i

1

0940+ 00

8004+ 01

0808+ 00

0068+ 01

0000-01

9829-01

. 9400+ 00

.7661 + 01

. 9270+ 00

. 5883+ 00

.6400-01

.8310-01

-7

. 9400+ 00

-1.7661+ 01

-7. 9270+ 0 0

-9. S 883+ 0 0

0. 0000+ 00

0.0000+ 00

E=tooMlf

Sicml=.?. mfhm-ns

MFP - 3S2 ~

53 8.5099-01 2.0000+ 01-8.3480-01 0.0000+ 00

S 4 1.02S 5+ 00 2.0000+ 01 -1.0060+ 00 0:0000+ 00

. . . .

55 1.3120+ 00 2.0000+ 01 -1.2870+ 00 0.0000+ 00

56 1.4618+ 00 2.0000+ 01 -1.4340+ 00 0.0000+ 00

57 1.5689+ 00 2.0000+ 01 -1.5390+ 00 0.0000+ 00

58 2.0113+ 00 2.0000+ 01 -1.9730+ 00 0.0000+ 00

59 2.21s2+ 00 2.0000

)+ 01 -2.1730+ 00 0.0000+ 00

13+ 00 2.0000+ 01 -2.2330+ 00 0.0000+ 00.276

2.3660+ 00

2.4160+ 00

2.5026+ 00

2.6983+ 00

2.7i26+ O0

2.7218+ 00

2.7636+ 00

2.8217+ 00

2.8288+ 00

3.0225+ 00

3.0s31+ 00

R i7&t

2.0000+01

2.0000+01

2.0000+ 01

2.0000+01

2.0000+01

2.0000+01

2.0000+01

-2.32iO+ O0

-2.3700+ 00

-2.4650+ 00

-2.6470+ 00

-2.6610+ 00

-2.6700+ 00

-2.7110+ 00

0:0000+00

0.0000+00

0.0000+00

0.0000+00

0.0000+ 00

0.0000+ 00

0.0000+ 00

0.0000+ 00

0.0000+ 00

0.0000+ 00

0.0000+ 00

Usr x

2.0000+01

2.0000+01

2.0000+01

2.0000+ 01

-2.7680+ 00

-2.77S0+ 00

-2.9650+ 00

-2.9960+ 00

:4+ 00 2.0000+ 01-3.1140+ 00 0.0000+ 00

73 5:i9~ 8+ O0 2.0000+ 01-3.1320+ 00 0:0000+ 00

74 3.2142+ 00 2.0000+ 01-3.1530+ 00 0,0000+ 00

75 3.2233+ 00 2.0000+ 01-3.1620+ 00 0.0000+ 00

76 3.2478+ 00 2.0000+ 01 -3.1860+ 00 0.0000+ 00

77 3.3314+ 00 2.0000+ 01-3.2680+ 00 0.0000+ 00

E= 14.00 MeV

sKm2T=2.42k?n6

MFP=4ssem

%

80

81

82

83

:

86

87

88

3.4170+ 00

3.4810+ 00

3.5383+ 00

3.6872+ 00

3,8442+ 00

4.0240+ 00

4,0930+ 00

4.1174+ 00

4.6520+00

4.7200+00

4.9310+00

2.0000+ 01-3.3620+ 00 0.0000+ 00

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+01

2.0000+01

-3

-3

-3

-3

-3

::

-4

-4

.4140+ 00

.4710+ 00

.6170+ 00

.7710+ 00

.9470+ 00

.0150+ 00

.0390+ 00

.6630+ 00

.6300+ 00

%370+ 00

o.

0.

0.

0.

0.

::

0.

0.

0.

0000+ 00

0000+ 00

0000+ 00

0000+ 00

0000+ 00

0000+ 00

0000+ 00

0000+ 00

0000+ 00

0000+ 00

+ 00 :

+ 00 2

.0000+ 01

.0000+ 01

.0000+ 01

.0000+ 01

.0000+ 01

.0000+ 01

.,0000+ 01

.0000+ 01

.0000+ 01

.0000+ 01

-4

-5

-6

8

0970+ 00

2920+ 00

8246+ 00

2371+ 00

6660-01

3642+ 00

9650+ 00

89

90

Ii i

103

104

105

106

107

5,

::

1.

$

;:

1960

3947

2000

0000

8000

,0000

;:;;

o.

0000+ 00

0000+ 00

8246+ 00

2371+ 00

5660-01

3642+ 00

9650+ 00

- i

- ;:

-7.

-9.

+ 00 2

-11 2

+ ()() 2

+ 00 2

+ 01 2

+ 00 2

+ 00 2

-i

-:

-7

-9

-8

6281+ 00

7940+ 00

-8.

1.

6281+ 00

7940+ 00

000 i

78


91/292

24000.50C

w

d id

ZAID S4DOQS

CT-NAT

tiRMcw

m-f

I v r i i

.

m-a

m.Asnc

m-m

AXDRRION

ZAID- DOD6DC

(% NAT

RamRums

tw-

.

Lij

...

t %jrn..................

/&irY?)

MT-fw

NALFWA

79

s.

~ .

u

f

i

%

~

3

/

.-

./

,.---

a +

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

s u

*4 SM

%dvuJ&mrev)

/

/

XUD - ~

ti - NAT

nwmlwas

MT-ml

HrAnNc

M. 4

IVTALINM,As17c

fl aa

/GjiFfu

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

W.Jw

)

ZUD

AIDOMQC

& Nm

mm

RMccs

MT-ma

PnomNmDD

.

m-m

DmrcIuuu m

..,

w -m

rnnluu

m

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

m-m

Hz-.3 FWD

MT-m

AxAwmDD

8


92/292

R E F E R E N C E :

Reaction

elwkic

(n,an)

(n,$n)

(n,n)a

(@z

(n,n2)

(n,n$)

(n,n4)

(n,n5)

(n,n6)

(n,n7)

(n,n8)

(n,n %)

(n,n10)

(n,n11)

(n,n12)

(n,nc)

(n,7)

(n,p)

(n$d)

(n,He)

(n,a)

Manganese 55

ZAID=25055.50C

SOURCE:NDF/B-VMAT=1325,

ape 508)

S u mm a r y D ocu men t a t ion of t h e N eu t ron a n d G a m m a R a y P r od uct ion C r os s S ect ion s of

Mn,

by S.

F . M ug h a bg ha b , con t a i ned i n E N D F -201

Dab A akabk


ZAID = 25055.50C

NE S= 12525 T= 30&K

ZAID = 25055.51C

NES=1578

T= 3000K

D -t e Rea ct ion

ZAID = 25055.50D

NE S = 263 T= 30&K

ZAI D = 25055.51D NE s= 263

T= 30trK

MuMgroup

ZAID = 25055.50M

30-Group

T=WFK

MOM Inf9mAh

Ab un d a n ce= 100. 00%

D en a it y = 7 .2 0 g m /cm 3

PhotomProduction Data - Yes

Heating Numbere - Local

E nergy Ra rLge - 10-] 1 t o 20 Me V

Ii8=tion Mdmdi2n

MT

;2

52

63

54

5s

66

57

::

60

61

62

1%

103

104

106

107

E mi n (M eV )

1.0000-11

i. 0413+ 01

1. 9 52 0+ 0 1

1. 10 00 +0 1

9. 0000+ 00

1.2811-01

1. 00 24+ 00

1. 31 58+ 00

1. S 570+ O 0

i . 9200+ 00

2. 23 95+ 00

2. 295S + 00

2. 31 08+ 00

2. 35 36+ 00

2. 40 96+ 00

2. 44 20+ 00

2. 47 37+ 00

; .;;g + ::

1: 8 430 +0 0

5 . 9 473 +0 0

1. 3 50 0+ 0 1

6.3310-01

%.(MW

2. 0000+ 01

2. 0000+ 01

2. 0000+ 01

2. 0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

%(Mev)

-1.0225+ 01

-1.9168+ 01

-7.9306+ 00

-8.0633+ 00

-1.2680-01

-9.8430-01

-1.2920+ 00

-1.S289+ 00

-1.8853+ 00

-2.1990+ 00

-2.2540+ 00

-2.2690+ 00

-2.3110+ 00

-2.3660+ 00

-2.3980+ 00

-2.4290+ 00

-2.4290+ 00

7.2704+ 00

-1.8098+ 00

-5.8388+ 00

-1.2380+ 01

-6.2160-01

Q@fev)

-1.0225+ 01

-1.9168+ 01

-7.9306+ 00

-8.0633+ 00

0.0000+ 00

0.0000+ 00

0.0000+ 00

0.0000+ 00

0.0000+ 00

0.0000+ 00

0.0000+ 00

0.0000+ 00

0.0000+ 00

0.0000+ 00

0.0000+ 00

0.0000+ 00

-2.4290+ 00

7.2704+ 00

-1.8098+ 00

-S.8388+ 00

-1.2380+ 01

-6.2160-01

THERMAL

Slcmr = 14.66 bama

MFP=omrun

E=l.06MV

mm?=w? bunu

MFP-4DOc+n

E-14.00W

SItZVT = 25 7 bna

UFP = 491 em

80


93/292

25055.50C

t - ~ - -

ifkfi.yd..

..w.... ---- --

id td

N&m mu% (A)

Ur-i

Ur. s -

WA.$7YC

.

m m

MSQRRION

-

I%j

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

Mr-m7

NALPNA

y/Jp_m

ML-66

Eo m

ENDIWJ8

m-am

Hml lnc

W-

AIDW=

ml-m

h 8NDF6u s

m-4

7VTAL~C

-

/K& j

. ._. _

f%s%y

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

~ ; j%YIA

. . . . . . . .

(Yf i j?

yiy_=

Mu-m

R un A N D4 8U S

m-m.

PnamN HOD

-

MT-w

DEWER)UM PROD

. ,,

MT-w

H E-S M OD

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

MT-Z07

ALPHAPROD

,


94/292

iron

Reaction

elastic

(n,2n)

(n,n)o

(n,n)p

(n,n1)

(n,n2)

(n,n3)

(n,n4)

(n,n5)

(n,n6)

(n,n7)

(n,n8)

(n,n9)

(n,n10)

(n,n11)

(n,n12)

(n,n13)

(n,n14)

(n,n15)

(n,n16)

(n,n17)

(n,n18)

(n,n19)

(n, t l 20)

(n,n21)

(n,n22)

(n,n23)

(n,n24)

(n,n25)

(n,n26)

(n,n27)

(n,n2.s)

(n,n29)

(n,n30)

(n,n31)

(n,n32)

(n,n33)

(n,n34)

(n,n35)

(n,n36)

(n,u37)

(n,n38)

(n,n39)

f:::;:;)

(n,-j)

(n$p)

(n,d)

(n$t)

[~;~Ie)

ZAID=26000.55C

SOURCE: Group T-2 (MAT=26o, File /T2/PGY/FE5/LAFE)

REFERENCE: Evaluated Neutron-Induced Cross Sections for 54,56Fe to 40 MeV ,

by E, D. Arthur and P. G. Young

Los Alamos National Laboratory report LA-8826-MS (December 1980)

pat . A vailability

Continuous Energy

ZAID=26000.55C

NES=6S99

T=300K

Discrete Reaction

ZAID=26000,55D

NES=263

T=300K

Multigroup

ZAID=26000,55M

30-Group

T=300K

JsotoDe[nformation

Abundance= Natural

Density =7.86 gm/cm3

Evaluation Inform

ation

Photon-Production Data

Yes

Heating Numbers Local

Energy Range 10-11 to 20MeV

h~n

ati

MT E min (MeV) E = .. (MeVl

Ov(MeVl

2 i .0000 -11 2XOOO+ 0I .

16 i. 1399+ 01 2.0000+ 01 -1.1197+ 01

22 7.7515+ 00 2.0000+ 01 -7.6140+ 00

28

51

52

H

55

56

57

58

59

::

62

63

64

65

%

9. oi 30+ oo

8.6210-01

1 . 43 42 +0 0

2. 1228+ 00

2. 59 44 +0 0

2. 60 76 +0 0

2.7056+ 00

3. 00 00 +0 0

3 . 0 135 +0 0

3 . 0 135 +0 0

3. 1764+ 00

3. 1794+ 00

3. 2233+ 00

3. 3547+ 00

3. 40 54 +0 0

3.4311+ 00

3. 44 92 +0 0

3. 5072+ 00

2.

0000+01

2 . 0 00 0+ 0 1

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.0000+ 01

2.000o+ oi

-8:8530+ 00

-8.4680-01

-1,4084+ 00

-2.0851+ 00

-2.5384+ 00

-2.6613+ 00

-2.6576+ 00

-2.9417+ 00

-2.9590+ 00

-2.9600+ 00

-3.1200+ 00

-3.1230+ 00

-3.1661+ 00

-3.2952+ 00

-3.3450+ 00

-3.3702+ 00

-3.3880+ 00

-3.4450+ 00

68 3.5123+ 00 2.0000+ 01 -3.4500+ 00

69 3.6670+ 00 2.0000+ 01 -3.6019+ 00

---

------ --

70 3.6729+ 00 2.0000+ Oj -3.6070+ 00

71 3.8300+

A .Nuclear Cross Section hand book.pdf

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