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

Technical Report · Thu Sep 21 00:00:00 EDT 1978

DOI:https://doi.org/10.2172/6872032· OSTI ID:6872032

Ball, S J; Cleveland, J C; Conklin, J C; Hatta, M; Sanders, J P

Assistance was provided to NRC in evaluating and confirming ECCS analyses for the Fort St. Vrain (FSV) reactor in support of a 100% power license application. Comparisons of ORNL accident analyses with those of the applicant were generally in good agreement. Other work included further development of the ORTAP-FSV and ORECA codes and comparisons of data from several FSV scram tests with ORECA code predictions.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6872032
• Report Number(s): NUREG/CR-0256; ORNL/NUREG/TM-233
• Country of Publication: United States
• Language: English

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