High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research. Quarterly progress report, July 1, 1976--September 30, 1976
Technical Report
·
OSTI ID:7223443
Progress is summarized in the following areas: analysis of rod-withdrawal transients in the Fort St. Vrain reactor; dynamic modeling of HTGR steam generators, including a nonlinear model for the Vrain steam generator-reheater; and evaluation of the Reactor Emergency Cooling Analysis (RECA) code. (DG)
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 7223443
- Report Number(s):
- ORNL/NUREG/TM-66
- Country of Publication:
- United States
- Language:
- English
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OSTI ID:6468970
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BOILERS
COMPUTER CALCULATIONS
COMPUTER CODES
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HEAT TRANSFER
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
MATHEMATICAL MODELS
POWER REACTORS
R CODES
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
STEAM GENERATORS
TRANSIENTS
VAPOR GENERATORS
VRAIN REACTOR
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BOILERS
COMPUTER CALCULATIONS
COMPUTER CODES
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HEAT TRANSFER
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
MATHEMATICAL MODELS
POWER REACTORS
R CODES
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
STEAM GENERATORS
TRANSIENTS
VAPOR GENERATORS
VRAIN REACTOR