High-Temperature Gas-Cooled Reactor Safety Studies for the Division of Reactor Safety Research Quarterly Progress Report, October 1—December 31, 1978
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Denison Univ., Granville, OH (United States)
Further development of the ORECA code was done based on analyses of Fort St. Vrain (FSV) reactor test data. Work also continued on upgrading the ORTAP, BLAST, and FLODIS codes. Preliminary reverse-flow plume experiments for investigating the FSV upper plenum cover plate heating phenomenon were continued. Further assistance was given to NRC on FSV questions relating to their 100% power license application and the oscillation problem.
- 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:
- 6168805
- Report Number(s):
- NUREG/CR--0716; ORNL/NUREG/TM--314
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
COMPUTER CODES
ENRICHED URANIUM REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
MATHEMATICAL MODELS
POWER REACTORS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
TESTING
VRAIN REACTOR
220900* -- Nuclear Reactor Technology-- Reactor Safety
COMPUTER CODES
ENRICHED URANIUM REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
MATHEMATICAL MODELS
POWER REACTORS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
TESTING
VRAIN REACTOR