High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research. Quarterly progress report, April 1-June 30, 1981
Technical Report
·
OSTI ID:5112708
Work continued on the development of the ORTAP and ORECA codes, which are used in accident sequence analyses of the Fort St. Vrain high-temperature gas-cooled reactor (HTGR). Initial work was also done on an HTGR severe accident sequence analysis task, which will study low-probability accidents that lead to core damage.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5112708
- Report Number(s):
- NUREG/CR-2221-Vol.2; ORNL/TM-8091; ON: TI86000933
- 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, July 1-September 30, 1981
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, January 1-March 31, 1980
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, April 1--June 30, 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, January 1-March 31, 1980
Technical Report
·
Fri Aug 01 00:00:00 EDT 1980
·
OSTI ID:6349816
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210300 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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ACCIDENTS
COMPUTER CODES
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GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
O CODES
POWER REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
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