Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October--December 1975
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
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36 MATERIALS SCIENCE
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CHALCOGENIDES
COMPUTER CALCULATIONS
ECCS
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FUEL ELEMENTS
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MATHEMATICAL MODELS
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PERFORMANCE
PHYSICAL RADIATION EFFECTS
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PLUTONIUM DIOXIDE
PLUTONIUM OXIDES
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REACTOR OPERATION
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