High-Temperature Gas-Cooled Reactor safety studies for the Division of Reactor Safety Research quarterly progress report, October 1--December 31, 1977
Work continued on developing and refining the ORTAP-FSV code, a simulator of the dynamic behavior of the Fort St. Vrain reactor nuclear steam supply system. Preliminary comparisons were made of data obtained from a Fort St. Vrain reactor scram and predictions using the ORECA code, and the agreement was good.
- Research Organization:
- Oak Ridge National Lab., Tenn. (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5152087
- Report Number(s):
- ORNL/NUREG/TM-195
- Country of Publication:
- United States
- Language:
- English
Similar Records
High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research. Quarterly progress report, April 1--June 30, 1978
High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research. Quarterly progress report, July 1-September 30, 1981
High-Temperature Gas-Cooled Reactor Safety Studies for the Division of Reactor Safety Research Quarterly Progress Report, October 1—December 31, 1978
Technical Report
·
Thu Sep 21 00:00:00 EDT 1978
·
OSTI ID:6872032
High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research. Quarterly progress report, July 1-September 30, 1981
Technical Report
·
Thu Dec 31 23:00:00 EST 1981
·
OSTI ID:5330337
High-Temperature Gas-Cooled Reactor Safety Studies for the Division of Reactor Safety Research Quarterly Progress Report, October 1—December 31, 1978
Technical Report
·
Mon Apr 02 23:00:00 EST 1979
·
OSTI ID:6168805
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
COMPUTER CODES
ENRICHED URANIUM REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
MATHEMATICAL MODELS
O CODES
POWER REACTORS
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
SAFETY
SCRAM
SHUTDOWNS
TRANSIENTS
VRAIN REACTOR
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
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
O CODES
POWER REACTORS
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
SAFETY
SCRAM
SHUTDOWNS
TRANSIENTS
VRAIN REACTOR