High-temperature gas-cooled reactor safety studies for the Division of Accident Evaluation. Quarterly progress report, January 1-March 31, 1983. Volume 1

Technical Report · Tue Nov 01 04:00:00 EST 1983

OSTI ID:5492216

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

Work continued on high-temperature gas-cooled reactor safety research directed towards both the Fort St. Vrain and 2240-MW(t) lead plant reactors. Code development and verification activities addressed simulations of unrestricted core heatup accidents, steam generator and turbine-plant perturbations, and fission-product redistribution during severe accidents. Analyses and sensitivity studies of the lead plant thermal response were made for postulated severe accidents, and partial pressures of pertinent reactor materials were calculated for the resulting severe accident environment.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5492216
• Report Number(s): NUREG/CR-3492-Vol.1; ORNL/TM-8921/V1; ON: DE84002501
• Country of Publication: United States
• Language: English

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