High-temperature gas-cooled reactor safety studies for the Division of Accident Evaluation. Quarterly progress report, January 1-March 31, 1982

Technical Report · Wed Sep 01 00:00:00 EDT 1982

OSTI ID:5083348

Ball, S J; Clapp, Jr, N E; Cleveland, J C; Conklin, J C; Harrington, R M; Kelmers, A D; Kornegay, F C

Continuing code development work included improvements to the BLAST steam generator dynamics simulation for the Fort St. Vrain reactor and implementation of a simplified version of the core model CORTAP. Work continued on severe accident sequence analyses, including further work on the ORECA code three-dimensional core simulation and a new effort to review the fission-product release and transport methodology. Work was also started on a siting study for a 2240-MW(t) high temperature gas-cooled reactor plant design.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5083348
• Report Number(s): NUREG/CR-2874-Vol.1; ORNL/TM-8443-Vol.1; ON: DE82021854
• Country of Publication: United States
• Language: English

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