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 00:00:00 EST 1980

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

Ball, S. J. ^[1]; Cleveland, J. C. ^[1]; Conklin, J. C. ^[1]

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1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

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 intermediate 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 Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE; USNRC
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5713491
• Report Number(s): ORNL/NUREG/TM--366; NUREG/CR-1136
• Country of Publication: United States
• Language: English

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