High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety. Quarterly progress report, April 1, 1976--June 30, 1976
Technical Report
·
OSTI ID:7331163
Work during the reporting period was concentrated on further development of the ORTAP code and adapting it to simulations of specific Fort St. Vrain (FSV) reactor transients.
- Research Organization:
- Oak Ridge National Lab., Tenn. (USA)
- DOE Contract Number:
- W-7405-ENG-26; NRC-INA-40-551-75
- OSTI ID:
- 7331163
- Report Number(s):
- ORNL/NUREG/TM-43
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HTGR TYPE REACTORS
REACTOR SAFETY
RESEARCH PROGRAMS
COMPUTER CALCULATIONS
COMPUTER CODES
DEPRESSURIZATION
HEAT TRANSFER
O CODES
STEAM GENERATORS
TRANSIENTS
VRAIN REACTOR
BOILERS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
POWER REACTORS
REACTORS
SAFETY
VAPOR GENERATORS
220900* - Nuclear Reactor Technology- Reactor Safety
210300 - Power Reactors
Nonbreeding
Graphite Moderated
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HTGR TYPE REACTORS
REACTOR SAFETY
RESEARCH PROGRAMS
COMPUTER CALCULATIONS
COMPUTER CODES
DEPRESSURIZATION
HEAT TRANSFER
O CODES
STEAM GENERATORS
TRANSIENTS
VRAIN REACTOR
BOILERS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
POWER REACTORS
REACTORS
SAFETY
VAPOR GENERATORS
220900* - Nuclear Reactor Technology- Reactor Safety
210300 - Power Reactors
Nonbreeding
Graphite Moderated