A Nuclear Cross Section Data Handbook

Reaction
elastic
(n,~n)
(n,3n)
(n,n’1)
(n,n’2)
(n,n’.3)
(n,n’4)
(n,n’5)
(n,n’6)
(n,n’?)
(n,n’S)
(n,n’9)
(n,n’10)
[%;)
(n$p)
Tantalum – 181
ZAID=73181.50C
SOURCE: ENDF/B-V (MAT= 1285, Tape 502)
REFERENCE: “Ta–181 Evaluated Neutron Cross Sections,”
by R. J. Howerton, S. T. Perkins, R, C. Haight, and M. H. MacGregor
contained in ENDF–201
Continuous Energy
ZAID=73181.50C NES=6341 T=3000K
ZAID=73181.51C NES=753 T=300”K
D~crete Reaction
ZAID=73181.50D NES=263 T=30&K
ZAID=73181.51D NES=263 T=3000K
Multigroup
ZAID=73181.50M 3&Group T=30&’K
MT
1;
;:
52
53
54
5s
56
57
S8
59
60
1::
103
J30toDe Informat iou
Abundance= 99.996%
Density= 16.60 gm/cms
Evaluation Information
Photon-Production Data - Yes
Heating Numbers - Local
Energy Range – 10-] 1 to 20 MeV
J1.eac.tion Infer*
E~in(Mev) E~~=(MeV) Q~(MeV)
1.0000-11 2. 0000+01
7. 6725+00 2. 0000+01 -7. 6300+00
1. 4299+01 2. 0000+01 -1. 4220+01
6.2346-03 2. 0000+01 -6.2000-03
1.3686-01 2. 0000+01 -1.3610-01
1. S948-01 2. 0000+01 -1.5860-01
3.0318-01 2. 0000+01 -3.0150-01
3.3938-01
4.8489-01
2. 0000+01
2.0000+01
-3.3760-01
-4.8220-01
4.9776-01 2.0000+01 -4.9500-01
6.2346-01
7.2401-01
2.0000+01 -6.2000-01
2.0000+01-7.2000-01
9.3016-01 2.0000+01-9.2600-01
1.1997+00 2.0000+01-1.1930+00
1.0000-11 2.0000+01 6.0700+00
2.4003-01 2.0000+01-2.3870-01
Ch@ev)
-7.6300+00
-1.4220+01
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
-1.1930+00
6.0700+00
-2.3870-01
176
THERAIAL
sIcToT -27.34 *
uFP=o@rc?n
Jr.f.oo Mlv
sIclwr=t3ii4barns
MFP.2.W cm
Ir.14now
%K?l’=&% &rns
AtFP- 398cm
Nn4#
.mnqypnr