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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.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Greek National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Greek National Report
Greece has signed the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management on 5 September 1997. The Convention entered into force on 16 March 2000. The present report is the National Report of Greece for the Second Review Meeting to the Convention, which will take place 15-26 May 2006 at the IAEA in Vienna. The report has been prepared in accordance with the Guidelines regarding the Form and Structure of National Reports (IINFCIRC/604, 1 July 2002), established by the Contracting Parties under Article 29 of the Convention.