A Nuclear Cross Section Data Handbook

Reaction
ela8tic
(n,2n)
(n,n’1)
(m,n’2)
(Ia,n’s)
(n,n’4)
(n,n%)
(n,n’6)
(n,n’?)
(n,n’8)
(n,n’0)
(Il,n’lo)
(n,n’11)
(n,n’12)
*;)
(n,p)
Hafnium
ZAID=72000.50C
SOURCE: ENDF/11-V (MAT= 1372, Tape 501)
REFERENCE: “Evaluated Neutron Cross Sections for Natural Hafnium
and the Hafnium Isotopes 174, 176, 177, 178, 179, and 180,”
by M. K. Drake, D. A. Sargis, and Tin Maung
contained in ENDF–201 ZHERAUL
.wCIol’ = 111.43 bum
nFP=omm
Data A v~
Continuous Energy
2A,ID=72000.50C
NES=8270
Discrete Reaction
T=300’JK
ZA,ID=72000.50D
NES=263 T=300’JK
MT
2
i!!!
52
63
54
6S
66
57
58
%
61
62
1%
103
~tODe Informatio~
Abundance= Natural
Density= 13.31 gm/cm3
Evaluation Inforrnatiou
Photon-Production Data - No
Heating Numbers - Total
Energy Range – 10-11 to 20 MeV
Reaction Inf *
E~in(Mev) ll~~=(MOe.v)Q~(Mev)
1.0000-11 2. 0000+01
6. 1300+00 2. 0000+01 -6. 0700+00
9.3727-02 2. 0000+01 -9.3200-02
1.1364-01 2. 0000+01 -1.1300-01
2.5202-01 2. 0000+01 -2.5060-01
3.0900-01 2. 0000+01 -3.0700-01
3.2300-01 2. 0000+01 -3.2100-01
3.8718-01 2.0000+01 -3.8S00-01
4.1131-01 2.0000+01 -4.0900-01
4.2941-01 2.0000+01 -4.2700-01
6.1200-01 2.0000+01 -6.0900-01
5.5814-01 2.0000+01-5.6500-01
6.9434-01 2.0000+01-5.9100-01
6.3600-01 2.0000+01-6.3200-01
1.0000+00 2.0000+01-9.3200-02
1.0000-11 2.0000+01 7.1800+00
7.5000+00 2.0000+01 2.9000-01
QdMev)
-6.0700+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
-9.3200-02
7.1800+00
2.9000-01
174
E-1.00MaV
Suzt?l’ = 7.lM bum
UFP= X14 c+n
E= t4m WV
SIROT= 6,30 bwn.r
J4FP. 4XI m
MM#rA
10Z4L;N#.i5tlc
qg
N,c.4.&..