MORECA-2: Interactive simulator for modular high-temperature gas-cooled reactor core transients and heatup accidents with ATWS options
- 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. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 10116937
- Report Number(s):
- NUREG/CR-5945; ORNL/TM-12233; ON: TI93005715
- Resource Relation:
- Other Information: PBD: Dec 1992
- Country of Publication:
- United States
- Language:
- English
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