A Nuclear Cross Section Data Handbook

Reaction
elaatk
(n#l’l)
(Il,n’)sa
(rl,n’)su
(n,n’)sa
(n,n’)30
(rl,n’)3a
(n,n’)3a
(n,n’)3a
(Il,n’)scr
(n,n’)3a
(n,n’)3a
(n,rl’)3u
(n,m’)3a
(n,n’)3a
(n,n’)3a
(n,n’)3a
(a,n’)3a
(n,n’)3a
&,;j)Sa
(n,p)
(n,d)
(n,a)
Carbon
ZAID=6000.50C
SOURCE:ENDF/B-V(MAT=1306,
Tape 511)
REFERENCE: “Summary Documentation Carbon Evaluation ENDF/B-V MAT 1306,”
by C. Y. Fu and F. G. Perey
contained in ENDF–201
Jlata AvailabXty
Continuous Energy
ZAID=6000.50C NES=875 T=30@K
ZAID=6000.51C NES=876 T=3000K
Discrete Reaction
zAID=6fxlo.5oD NES=263 T=300’-’K
Multigroup
ZAID=6000.50M 30-Group T=300’JK
MT
2
51
52
53
::
56
57
58
69
60
61
62
63
64
6S
66
67
::
102
103
104
107
Mom ln&mm&u
Abundance=Natural
Denaity=2.25 gm/cm3
Photon-Production Data - Yes
Heating Nwnbem - had
Energy Range -10-” to 20 MeV
Emi.(Mev) lh..(kkv) Q~(Mev)
1.0000-11 2. 0000+01
4. 8121+00 2. 0000+01 -4. 4390+00
8. 2963+00 2. 0000+01 -7. 6S30+00
1. 0448+01 2. 0000+01 -9. 6380+00
1. 1166+01 2 .0000 +01 -1. 0300+01
1, 1761+01 2.0000+01 -1.0840+01
1,2196+01 2.0000+01 -1.1260+01
1.2738+01 2.0000+01 -1.17 S0+01
1.3280+01 2.0000+01 -1.22S0+01
1.3822+01 2.0000+01-1.2760+01
1.4364+01 2.0000+01 -1.32S0+01
1.4906+01 2.0000+01-1.3750+01
1.6448+01 2.0000+01-1.4250+01
1.6990+01 2.0000+01-1.4760+01
1.6532+01 2.0000+01-1.5250+01
1.7074+01 2.0000+01 -1.S7S0+01
1.7616+01 2.0000+01-1.6250+01
1.8158+01 2.0000+01-1.6750+01
1,8700+01 2,0000+01-1.7260+01
7.8865+00 2.0000+01-7.2750+00
1.0000-11 2.0000+01 4.9470+00
1.4500+01 2.0000+01 -1.2S88+01
1,52S0+01 2,0000+01-1.3733+01
6.1737+00 2.0000+01 -5.69S0+00
NOTE:(PLEASE SEE APPENDIX B)
%@fev)
0.0000+00
-7.2750+00
-7.2750+00
-7.2760+00
-7.27S0+00
-7.2750+00
-7.2750+00
-7.2750+00
-7.2760+00
-7.27S0+00
-7.27S0+00
-7.27S0+00
-7.2750+00
-7.27S0+00
-7.27S0+00
-7.27S0+00
-7.2750+00
-7.2760+00
-7.2750+00
4.9470+00
-1.2588+01
-1.3733+01
-6.6950+00
40
T?isiw.u
smlw’=4%banv
niw.lmcm
E=f&Mv
Smur.s.sshawu
Uw.s.uem
E-laohv
Smvl’-l.slbanw
Mw-e.mcm