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Goluoglu, Sedat; Leppanen, Jaakko; Petrie, Lester M. Jr.; Dunn, Michael E.
Oak Ridge National Laboratory (United States). Funding organisation: NNSA USDOE - National Nuclear Security Administration (United States)2010
Oak Ridge National Laboratory (United States). Funding organisation: NNSA USDOE - National Nuclear Security Administration (United States)2010
AbstractAbstract
[en] SCALE code system is developed and maintained by Oak Ridge National Laboratory to perform criticality safety, reactor analysis, radiation shielding, and spent fuel characterization for nuclear facilities and transportation/storage package designs. SCALE is a modular code system that includes several codes which use either Monte Carlo or discrete ordinates solution methodologies for solving relevant neutral particle transport equations. This paper describes some of the key capabilities of the Monte Carlo criticality safety codes within the SCALE code system.
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1 Oct 2010; vp; Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2010 (SNA + MC 2010); Tokyo (Japan); 17-21 Oct 2010; DP0902090; DPDP097; AC05-00OR22725; Available from Oak Ridge National Laboratory, Oak Ridge, TN (US)
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Miscellaneous
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Conference
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