High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research. Quarterly progress report, January 1, 1977--March 31, 1977
Technical Report
·
OSTI ID:7105181
Work on HTGR safety studies this quarter was primarily on refining the ORTAP code for the Fort St. Vrain Reactor to cover wider operating ranges. General Atomic Company's TAP program was implemented on the IBM 360 system at ORNL.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 7105181
- Report Number(s):
- ORNL/NUREG/TM-115
- 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, 1977
High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research. Quarterly progress report, October 1, 1976--December 31, 1976
High-Temperature Gas-Cooled Reactor safety studies for the Division of Reactor Safety Research quarterly progress report, October 1--December 31, 1977
Technical Report
·
Tue Sep 20 00:00:00 EDT 1977
·
OSTI ID:7295759
High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research. Quarterly progress report, October 1, 1976--December 31, 1976
Technical Report
·
Mon Feb 21 23:00:00 EST 1977
·
OSTI ID:7311008
High-Temperature Gas-Cooled Reactor safety studies for the Division of Reactor Safety Research quarterly progress report, October 1--December 31, 1977
Technical Report
·
Sun Mar 12 23:00:00 EST 1978
·
OSTI ID:5152087
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BOILERS
COMPUTER CODES
DEPRESSURIZATION
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
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HELIUM COOLED REACTORS
HTGR TYPE REACTORS
O CODES
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VRAIN REACTOR
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BOILERS
COMPUTER CODES
DEPRESSURIZATION
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HEAT TRANSFER
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
O CODES
POWER REACTORS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
STEAM GENERATORS
TRANSIENTS
VAPOR GENERATORS
VRAIN REACTOR