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Light Water Reactor Safety Research Program: Quarterly Report, October - December 1977 (Vol. 6)

Technical Report ·
DOI:https://doi.org/10.2172/6594461· OSTI ID:6594461
Progress is summarized in the following areas: molten core-concrete interactions studies, steam explosion phenomena, statistical analysis of peak clad temperature probability distribution following loss of coolant, and RELAP code development for treatment of PWR upper head injection ECCS.
Research Organization:
Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)
Sponsoring Organization:
USDOE; USNRC
DOE Contract Number:
EY-76-C-04-0789;
Other Award/Contract Number:
DOE-40-550-75
NRC-FIN-A1019
NRC-FIN-A1030
NRC-FIN-1205
NRC-FIN-A1207
OSTI ID:
6594461
Report Number(s):
SAND--78-0600(Vol.6); NUREG/CR-0307(Vol.6)
Country of Publication:
United States
Language:
English

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