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

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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.