High-temperature gas-cooled-reactor safety studies for the Division of Accident Evaluation. Quarterly progress report, July 1-September 30, 1982. Volume 3

Technical Report · Sun May 01 00:00:00 EDT 1983

OSTI ID:6067997

Ball, S J; Clapp, Jr, N E; Cleveland, J C; Conklin, J C; Harrington, R M; Kelmers, A D; Lindemer, T B; Siman-Tov, I

Continuing high-temperature gas-cooled reactor safety code development efforts included work on the overall nuclear steam supply system code ORTAP, versions of the three-dimensional core code ORECA for both Fort St. Vrain and the 2240-MW(t) lead plant, the BLAST steam generator code, and a simplified core model code called SCORE. Investigations were also continued to determine the status of fission-product source-term methodology applicable to postulated severe accidents.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6067997
• Report Number(s): NUREG/CR-2874-Vol.3; ORNL/TM-8443/Vol.3; ON: DE83011872
• Country of Publication: United States
• Language: English

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