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Ball, S.J.; Nypaver, D.J.
Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; Oak Ridge National Lab., TN (United States). Funding organisation: Nuclear Regulatory Commission, Washington, DC (United States)1992
Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; Oak Ridge National Lab., TN (United States). Funding organisation: Nuclear Regulatory Commission, Washington, DC (United States)1992
AbstractAbstract
[en] 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
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Dec 1992; 70 p; ORNL/TM--12233; CONTRACT AC05-84OR21400; OSTI as TI93005715; NTIS; INIS; GPO
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Report
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INIS VolumeINIS Volume
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