MORECA-2: Interactive simulator for modular high-temperature gas-cooled reactor core transients and heatup accidents with ATWS options

Technical Report · Tue Dec 01 00:00:00 EST 1992

OSTI ID:7042696

Ball, S J; Nypaver, D J ^[1]

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1. Oak Ridge National Lab., TN (United States)

This is a follow-up to an earlier report documenting the MORECA code, an interactive simulation tool for performing independent analyses of postulated modular high-temperature gascooled reactor (MHTGR) core transients and heatup accidents. This research was performed at Oak Ridge National Laboratory to assist the Nuclear Regulator Commission in preliminary determinations of licensability of the US Department of Energy reference design of a standard MHTGR. The additional features of MORECA documented in this report are the interactive workstation capabilities and the options for studying anticipated transients without scram events.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; Oak Ridge National Lab., TN (United States)
• Sponsoring Organization: USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 7042696
• Report Number(s): NUREG/CR-5945; ORNL/TM-12233; ON: TI93005715
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
HTGR TYPE REACTORS
REACTOR ACCIDENTS
TRANSIENTS
COMPUTERIZED SIMULATION
ATWS
HEATING
M CODES
REACTOR CORES
ACCIDENTS
COMPUTER CODES
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
REACTOR COMPONENTS
REACTORS
SIMULATION
220900* - Nuclear Reactor Technology- Reactor Safety
210300 - Power Reactors
Nonbreeding
Graphite Moderated
990200 - Mathematics & Computers