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LA-11711-M
Manua l
C3
. ; , ,
, .
: :; . , ,
EPRODUCTION
:.
..,,
,:,
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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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111
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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
176
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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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.. . . . . . . . . . .
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228
230
232
234
236
238
240
242
244
246
248
250
252
254
256
258
260
262
264
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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
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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
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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
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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
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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
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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.
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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
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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 :
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(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
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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
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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
)
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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).
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\
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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).
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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
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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
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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
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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
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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
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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
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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
~
C on t in uou s E n er gy
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
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23000.50C
Kiil
77
w-i
IV 8
..._
lr-fol
Wo.
aamosmc
V hw
xAiDssnw vc
v-m
$AID8aouvmc
v-m
h swwmm
mr-
-
Mm.mu
iliz
D
xAms800vJm
v-w
R9m~
%Gwl lnD
&t%mG
........... ... ..
u-m
Alwu-
9
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Chromium
ZAID=24000.50C
SOURCE: ENDF/B-V (MAT= 1324, Tape 512)
REFERENCE: Summary Documentation Natural Cbromium Evaluation EN DF/BV MAT= 1324,
by A. Prince and T. W. BurI
contained in ENDF-201
Continuous Energy
ZA1D=24000.50C NES=1105O T=300K
ZAID=24000,51C NES=1927
T=300K
Discrete Reaction
ZAID=24000.50D
NES=263
T=300K
Multigroup
ZAID=24000.50M 30-Group
T=300K
Js
oto~e I
nformation
Abundance= Natural
Density=7,20 grn/cm$
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
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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
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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
C on t in uou s E n er gy
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
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93/292
25055.50C
t - ~ - -
ifkfi.yd..
..w.... ---- --
id td
N&m mu% (A)
Ur-i
Ur. s -
WA.$7YC
.
m m
MSQRRION
-
I%j
..................
Mr-m7
NALPNA
y/Jp_m
ML-66
Eo m
ENDIWJ8
m-am
Hml lnc
W-
AIDW=
ml-m
h 8NDF6u s
m-4
7VTAL~C
-
/K& j
. ._. _
f%s%y
. . . . . . . . . . . . . . . . . .
~ ; j%YIA
. . . . . . . .
(Yf i j?
yiy_=
Mu-m
R un A N D4 8U S
m-m.
PnamN HOD
-
MT-w
DEWER)UM PROD
. ,,
MT-w
H E-S M OD
. . . . . . . . . . . . . . . . . .
MT-Z07
ALPHAPROD
,
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iron
Reaction
elastic
(n,2n)
(n,n)o
(n,n)p
(n,n1)
(n,n2)
(n,n3)
(n,n4)
(n,n5)
(n,n6)
(n,n7)
(n,n8)
(n,n9)
(n,n10)
(n,n11)
(n,n12)
(n,n13)
(n,n14)
(n,n15)
(n,n16)
(n,n17)
(n,n18)
(n,n19)
(n, t l 20)
(n,n21)
(n,n22)
(n,n23)
(n,n24)
(n,n25)
(n,n26)
(n,n27)
(n,n2.s)
(n,n29)
(n,n30)
(n,n31)
(n,n32)
(n,n33)
(n,n34)
(n,n35)
(n,n36)
(n,u37)
(n,n38)
(n,n39)
f:::;:;)
(n,-j)
(n$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+
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