High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research. Quarterly progress report, January 1-March 31, 1979

Technical Report · Mon Oct 01 04:00:00 EDT 1979

DOI:https://doi.org/10.2172/5802944· OSTI ID:5802944

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

Further development work was done on the ORECA, BLAST, and FLODIS codes. BLAST was adapted to the West German THTR steam generator design. The refurbishing of the FLODIS code was completed, and sample calculations of design-basis depressurization accidents (DBDAs) and loss-of-forced-convection (LOFC) accidents were run to make comparisons with other calculations. Followup investigations were also made of the Fort St. Vrain (FSV) reactor oscillation problems.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5802944
• Report Number(s): NUREG/CR-0899; ORNL/NUREG/TM-336
• Country of Publication: United States
• Language: English

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