A Nuclear Cross Section Data Handbook

Reaction
elwkic
(n,an)
(n,$n)
(n,n’)a
(@z
(n,n’2)
(n,n’$)
(n,n’4)
(n,n’5)
(n,n’6)
(n,n’7)
(n,n’8)
(n,n%)
(n,n’10)
(n,n’11)
(n,n’12)
(n,n’c)
(n,7)
(n,p)
(n$d)
(n,’He)
(n,a)
Manganese – 55
ZAID=25055.50C
SOURCE:ENDF/B-V(MAT=1325,
Tape 508)
REFERENCE: ‘Summary Documentation of the Neutron and Gamma Ray Production Cross Sectionsof Mn,”
by S. F. Mughabghab, contained in ENDF-201
Dab Av“’” akabk
Continuous Energy
ZAID=25055.50C NES=12525 T=30&K
ZAID=25055.51C NES=1578 T=3000K
D-te Reaction
ZAID=25055.50D NES=263 T=30&K
ZAID=25055.51D NEs=263 T=30tr’K
MuMgroup
ZAID=25055.50M 30-Group T=WF’K
MT
;2
52
63
54
5s
66
57
::
60
61
62
1%
103
104
106
107
MOM Inf9mAh
Abundance= 100.00%
Denaity=7.20 gm/cm3
PhotomProduction Data - Yes
Heating Numbere - Local
Energy RarLge - 10-] 1 to 20 MeV
Ii8=tion Mdmdi2n
Emin (MeV)
1.0000-11
i. 0413+01
1. 9520+01
1. 1000+01
9. 0000+00
1.2811-01
1. 0024+00
1. 3158+00
1. S570+O0
i . 9200+00
2. 2395+00
2. 295S+00
2. 3108+00
2. 3536+00
2. 4096+00
2. 4420+00
2. 4737+00
; .;;g+::
1: 8430+00
5. 9473+00
1. 3500+01
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
80
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