High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research. Quarterly progress report, April 1-June 30, 1981

Technical Report · Sun Nov 01 00:00:00 EST 1981

OSTI ID:5112708

Ball, S J; Cleveland, J C; Conklin, J C; Harrington, R M

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

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HTGR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
RESEARCH PROGRAMS
VRAIN REACTOR
COMPUTER CODES
O CODES
ACCIDENTS
ENRICHED URANIUM REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
POWER REACTORS
REACTORS
SAFETY
220900* - Nuclear Reactor Technology- Reactor Safety
210300 - Power Reactors
Nonbreeding
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