High-temperature gas-cooled reactor safety studies for the division of accident evaluation. Quarterly progress report, October 1-December 31, 1982

Technical Report · Mon Aug 01 00:00:00 EDT 1983

OSTI ID:5870346

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

Work continued on high-temperature gas-cooled reactor safety code development, including both the Fort St. Vrain and the 2240-MW(t) lead plant versions of the three-dimensional core code ORECA, the BLAST steam generator code, and a simplified core model code called SCORE. Oak Ridge National Laboratory participated in the Nuclear Regulatory Commission siting study for the lead plant with three other laboratories. Investigations 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: 5870346
• Report Number(s): NUREG/CR-2874-Vol.4; ORNL/TM-8443/V4; ON: DE83016221
• Country of Publication: United States
• Language: English

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