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

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The Radiation Safety Information Computational Center (RSICC) collects, analyzes, maintains, and distributes software in the areas of radiation transport and safety. RSICC resides in the Nuclear Energy and Fuel Cycle Division (NEFCD) at Oak Ridge National Laboratory.