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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.
United Arab Emirates, First National Report on Compliance with the Obligations of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
United Arab Emirates, First National Report on Compliance with the Obligations of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
A.1 This is the United Arab Emirates (UAE) first national report on compliance with the obligations of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (the Joint Convention). The UAE deposited its instrument of accession to the Joint Convention on 31 July 2009 and under Article (40) the Joint Convention entered into force for the UAE 90 days later on 29 October 2009. A.2 The report describes the basic policy and legal framework being established by the UAE for spent fuel management and radioactive waste management.