High-temperature gas-cooled reactor safety studies for the Division of Accident Evaluation. Quarterly progress report, April 1-June 30, 1983. Volume 2

Technical Report · Sun Jan 01 04:00:00 EST 1984

OSTI ID:5491239

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

Work on postulated severe accident sequence code development and application continued both for the Fort St. Vrain and 2240-MW(t) lead plant designs. Initial experiments on high-temperature gas-cooled reactor (HTGR) fission-product release and transport were run in an existing high-temperature (> 2000/sup 0/C) graphite-resistance furnace. Initial work was done on a cooperative study of HTGR safety research needs.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5491239
• Report Number(s): NUREG/CR-3492-Vol.2; ORNL/TM-8921-Vol.2; ON: DE84004789
• Country of Publication: United States
• Language: English

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