High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research. Quarterly progress report, April 1--June 30, 1978

Technical Report · Thu Sep 21 00:00:00 EDT 1978

OSTI ID:6872032

Ball, S J; Cleveland, J C; Conklin, J C; Hatta, M; Sanders, J P

Assistance was provided to NRC in evaluating and confirming ECCS analyses for the Fort St. Vrain (FSV) reactor in support of a 100% power license application. Comparisons of ORNL accident analyses with those of the applicant were generally in good agreement. Other work included further development of the ORTAP-FSV and ORECA codes and comparisons of data from several FSV scram tests with ORECA code predictions.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6872032
• Report Number(s): NUREG/CR-0256; ORNL/NUREG/TM-233
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HTGR TYPE REACTORS
REACTOR SAFETY
VRAIN REACTOR
LOSS OF FLOW
SCRAM
ECCS
RESEARCH PROGRAMS
STEAM SYSTEMS
ACCIDENTS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTOR SHUTDOWN
REACTORS
SAFETY
SHUTDOWNS
220900* - Nuclear Reactor Technology- Reactor Safety
210300 - Power Reactors
Nonbreeding
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