High-Temperature Gas-Cooled Reactor Safety Studies for the Division of Reactor Safety Research Quarterly Progress Report, April 1-June 30, 1978

Technical Report · Sun Oct 01 00:00:00 EDT 1978

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

Ball, S. J. ^[1]; Cleveland, J. C. ^[1]; Conklin, J. C. ^[1]; Hatta, M. ^[1]; Sanders, J. P. ^[1]

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1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

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 Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE; USNRC
• DOE Contract Number: W-7405-ENG-26
• Other Award/Contract Number: DOE-40-551-75; NRC-FIN-B0122-7
• OSTI ID: 6872032
• Report Number(s): ORNL/NUREG/TM--233; NUREG/CR-0256
• Country of Publication: United States
• Language: English

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