High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research. Quarterly progress report, July 1-September 30, 1979

Technical Report · Tue Jan 01 04:00:00 EST 1980

DOI:https://doi.org/10.2172/5713491· OSTI ID:5713491

Ball, S J; Cleveland, J C; Conklin, J C

Further development work was done on the ORTAP and BLAST codes. A new improved model of the Fort St. Vrain (FSV) reactor turbine-generator plant (ORTURB) was developed for use both as a stand-alone code and as a part of the ORTAP system code. Additional work was done on FSV licensing questions. The intermdiate heat transfer experiment for investigating FSV upper-plenum reverse-flow plumes was assembled and checked, and an on-line computer was set up to acquire and analyze the data.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5713491
• Report Number(s): NUREG/CR-1136; ORNL/NUREG/TM-366
• Country of Publication: United States
• Language: English

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