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U.S. Department of Energy
Office of Scientific and Technical Information

Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October--December 1975

Technical Report ·
DOI:https://doi.org/10.2172/7149470· OSTI ID:7149470
Light water reactor safety activities performed during October--December 1975 are reported. The blowdown heat transfer tests series of the Semiscale Mod-1 test program was completed. In the LOFT Program, preparations were made for nonnuclear testing. The Thermal Fuels Behavior Program completed a power-cooling-mismatch test and an irradiation effects test on PWR-type fuel rods. Model development and verification efforts of the Reactor Behavior Program included developing new analysis models for the RELAP4 computer code, subroutines for the FRAP-S and FRAP-T codes, and new models for predicting reactor fuel restructuring and zircaloy cladding behavior; an analysis of post-CHF fuel behavior was made using FRAP-T.
Research Organization:
Idaho National Engineering Lab., Idaho Falls (USA)
DOE Contract Number:
E(10-1)-1375
OSTI ID:
7149470
Report Number(s):
ANCR-NUREG-1301
Country of Publication:
United States
Language:
English