Package Details


Computer Code Name: COBRA-EN

Computer Code Number: P00507

Thermal-Hydraulic Transient Analysis of Reactor Cores

Keywords:
reactor physics
bwr
reactor accident
thermal hydraulics
lwr
heat transfer


Computers:
PC X86
MACINTOSH


Operating Systems:
LINUX
OSX
WINDOWS


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.