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N-Reactor Spent Nuclear Fuel Criticality Calculations
N-Reactor Spent Nuclear Fuel Criticality Calculations
The purpose of this calculation is to characterize the criticality safety aspects of N-Reactor fuel stored in a Department of Energy spent nuclear fuel (DOE-SNF) canister that contains four Multi-Canister Overpacks (MCO's). These calculations will be done to support the analysis that will be done to demonstrate concept viability related to pre-emplacement storage and use in the Monitored Geologic Repository (MGR) environment for the pre-closure time frame.
OECD/NEA: Slovak Republic
OECD/NEA: Slovak Republic
National Report of the Slovak Republic, June 2008
National Report of the Slovak Republic, June 2008
National Report of the Slovak Republic, August 2011
National Report of the Slovak Republic, August 2011
National Report of the Slovak Republic, April 2003
National Report of the Slovak Republic, April 2003
Nuclear Regulatory Authority of the Slovak Republic: 2011 Annual Report
Nuclear Regulatory Authority of the Slovak Republic: 2011 Annual Report
The year 2011 was the year that marked the global nuclear industry and influenced the attitudes and activities of many professional, scientific and commercial organizations and spurred public interest in this branch of industry. Probably the whole world reacted to the natural disaster that struck Japan and damaged the nuclear power plant at Fukushima, Slovakia not excluded.