High-Temperature Gas-Cooled Reactor safety studies for the Division of Accident Evaluation. Quarterly progress report, July 1-September 30, 1985. Volume 3

Technical Report · Tue Apr 01 04:00:00 EST 1986

OSTI ID:5706107

Ball, S J; Cleveland, J C; Conklin, J C; Harrington, R M; Wilson, J H

Further accident scenario analyses were done using simulations for the modular High-Temperature Gas-Cooled Reactor (HTGR), including an uncertainty analysis of the reactor vessel axial temperatures for long-term heatup accidents. More sections of the HTGR Safety Handbook were completed. Several licensing-related tasks were completed for the Fort St. Vrain HTGR.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5706107
• Report Number(s): NUREG/CR-4402-Vol.3; ORNL/TM-9798-Vol.3; ON: TI86009741
• Country of Publication: United States
• Language: English

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