Computer Code Name: COBRA-EN

Computer Code Number: P00507

Thermal-Hydraulic Transient Analysis of Reactor Cores.

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

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

123ABCDEFGHIJKLMNOPQRSTUVWXYZ

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.