Site Navigation
Package Details
Computer Code Name: COBRA-EN
Computer Code Number: P00507
Thermal-Hydraulic Transient Analysis of Reactor Cores.
Keywords:
heat transfer
lwr
reactor accident
reactor physics
thermal hydraulics
bwr
Computers:
PC X86
MACINTOSH
Operating Systems:
WINDOWS
LINUX
OSX
Languages:
FORTRAN 66
Publications:
Report no. 1010/1
Distribution Media:
P00507 MNYCP -----1 CD-ROM DISC
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) is a Department of Energy Specialized Information Analysis Center (SIAC) authorized to collect, analyze, maintain, and distribute computer software and data sets in the areas of radiation transport and safety. RSICC resides in the
Reactor and Nuclear Systems Division (RNSD)
at
Oak Ridge National Laboratory
.