High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research. Quarterly progress report, July 1--September 30, 1978

Technical Report · Wed Jan 24 23:00:00 EST 1979

OSTI ID:6069009

Ball, S J; Cleveland, J C; Conklin, J C

Further assistance was provided to the Nuclear Regulatory Commission (NRC) in confirming emergency core cooling system (ECCS) analyses of the Fort St. Vrain (FSV) reactor in support of a 100% power license application. Comparisons of FSV data from a scram test at 50% power with ORECA code predictions were also made. Other work included further development of the FSV simulation codes.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6069009
• Report Number(s): NUREG/CR-0592; ORNL/NUREG/TM-293
• Country of Publication: United States
• Language: English

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