A Nuclear Cross Section Data Handbook

Reaction
elaetic
(n,2n)
(n,Sn)
(n,f)
(n,n’f )
(n,2nf)
(n,n’1)
(n,n’2)
(n,n’3)
[:::::;
(n,n’6)
(n,n’7)
(n,n’S)
(n,n’9)
(n,n’10)
(n,n’11)
(n,n’12)
(n,n’13)
(n,n’14)
(n,n’15)
(n,n’16)
(n,n’c)
(n,-f)
Uranium – 235
ZAID=92235.50C
SOURCE: ENDF/B-V (MAT= 1395, Tape 511)
REFERENCE: “Summary Documentation for 235U~
by M. R. Bhat, contained in ENDF-201
j2&&Availabili ty
Continuous Energy
ZAID=92235.50C NES=5725
ZAID=92235.51C NES=1392
ZAID=92235.53C NES=2685
ZAID=92235.54C NES=2671
ZAID=92235.56C “NES=1729
ZAID=92235.57C NES=1319
ZAID=92235.58C NES=1038
ZAID=92235.59C NES=968
Discrete Reaction
ZAID=92235.50D NES=263
Multigroup
ZAID=92235.50M 30-Group
.laotom lnforma tioq
Abundance= O.7200~o
Density =18.811 gm/cm3
valuation Informatioq Photon-Production Data - Yes
Heating Numbers - Local
Energy Range – 10-11 to 20 MeV
Reaction Information
T=301YK
T=30W’K
T=60WK
T=90WK
T=120W’K
T.120000”K
T=1200000”K
T=1200wK
T=300”K
T=300”K
MT E-i. ...... (MeV) , E~..(MeV) Qw(MeV) Q .[Mev)
2 1.0000-1’1 2’:0000+01 ‘-- ‘ ‘
16 5. 3288+00 2. 0000+01 -5. 3060+00 -5. 3060+00
17
19
20
21
1.2199+01
i .0000 -11
s.Sooo+oo
1. 2200+01
2.0000+01
2.0000+01
2. 0000+01
2. 0000+01
-1 .2147 +01
1 .94( )2+02
1. 9402+02
1.9402+02
-1.2147+01
1. 9402+02
1. 9402+02
1.9402+02
S1 1.3056-02 2. 0000+01 -1.3000-02 0.0000+00
52 4.9813-02 2. 0000+01 -4.9600-02 0.0000+00
53 8.3969-02 2. 0000+01 -8.3600-02 0.0000+00
64
66
1.0294-01
1.4984-01 ---
2.0000+01 -I.02E
2.0000+01-1.4920-01
50-01 0.0000+00
0.0000+00
S6 ~:7274-01 2.0000+Oi -i.7200-01 0.0000+00
67 2.3S00-01 2.0000+01 -2.3400-01 0.0000+00
58
59
2.6915-01
3.9971-01
2.0000+01-2.6800-01
2.0000+01 -3.9800-01
0.0000+00
0.0000+00
60 6.9966-01 2.0000+01 -5.9700-01 O.0000+1
61
62
i:OOOO+OO
2.0000+00
2.0000+01
2.0000+01
-9.9S76-01
-1.9915+00
0.0000+it
0.0000+00
63 3.0001+00 2.0000+01 -2.9873+00 0.0000+00
64 4.0001+00 2.0000+01 -3.9830+00 0.0000+00
65
66
S.0002+00
6.0002+00
2.0000+01 -4.9788+00
2.0000+01-5.9746+00
0.0000+00
0.0000+00
9i 9.5000-01 2.0000+01 -9.4594-01 -9.4[ 594-01
102 1.0000-11 2.0000+01 6.5451+00 6.5451+00
212
THERMAL
Siclvl’=tw?mw
MFP.0D9 m
E=1.00kV
Sin-or= 6Af blw?u
k(FP= 3J23cm
E=14a3Mev
SIClUT=S&4 krns
MFP=9.&5e7n
.hw411A
,nmufA&.mc
(n&)