Site Navigation
Package Details
Computer Code Name: JENDL-1
Computer Code Number: D00070
Japanese Evaluated Neutron Cross Section Data in ENDF/B-IV Format.
Keywords:
evaluated neutron cross sections
Computers:
ALL COMPUTERS
Operating Systems:
Languages:
Publications:
NEANDC(J)-59L (JAERI-1261)
Distribution Media:
D00070 ALLCP -----2 DS/HD 5.25 (1.2MB) DOS
1
2
3
A
B
C
D
E
F
G
H
I
J
K
L
M
N
O
P
Q
R
S
T
U
V
W
X
Y
Z
FAQ
|
ORNL Home
|
DOE
|
Site Map
|
Security Notice
The Radiation Safety Information Computational Center (RSICC) collects, analyzes, maintains, and distributes software in the areas of radiation transport and safety. RSICC resides in the
Nuclear Energy and Fuel Cycle Division (NEFCD)
at
Oak Ridge National Laboratory
.