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
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.