High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research. Quarterly progress report, April 1--June 30, 1977
Technical Report
·
OSTI ID:7295759
HTGR safety studies concentrated on detailed investigations of postulated Fort St. Vrain rod-withdrawal accidents. General Atomic Company's TAP program for analysis of HTGR nuclear steam supply system performance transients was implemented on the local IBM 360 computers, and the results of sample problem runs appear to be in reasonable agreement with those published by General Atomic.
- Research Organization:
- Oak Ridge National Lab., Tenn. (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 7295759
- Report Number(s):
- ORNL/NUREG/TM-138
- 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, January 1, 1977--March 31, 1977
High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research. Quarterly progress report, July 1, 1976--September 30, 1976
Simulation of the response of the Fort St. Vrain high temperature gas cooled reactor system to a postulated rod withdrawal accident
Technical Report
·
Tue May 31 00:00:00 EDT 1977
·
OSTI ID:7105181
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
·
Sun Nov 28 23:00:00 EST 1976
·
OSTI ID:7223443
Simulation of the response of the Fort St. Vrain high temperature gas cooled reactor system to a postulated rod withdrawal accident
Conference
·
Fri Dec 31 23:00:00 EST 1976
·
OSTI ID:5450867
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HELIUM COOLED REACTORS
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MATHEMATICAL MODELS
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REACTOR ACCIDENTS
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