Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
This design calculation revises and updates the previous criticality evaluation for the canister handling, transfer and staging operations to be performed in the Canister Handling Facility (CHF) documented in BSC (Bechtel SAIC Company) 2004 (DIRS 167614).
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Slides - 2014 WM Symposia, March 2-6, 2014, Phoenix, AZ
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
This report presents a comprehensive description of the post-closure radiological safety assess- ment of a repository for spent fuel (SF), vitrified high-level waste (HLW) from the reprocessing of spent fuel and long-lived intermediate-level waste (ILW), sited in the Opalinus Clay of the Zürcher Weinland in northern Switzerland. This assessment has been carried out as part of the technical basis for Project Entsorgungsnachweis1, which also includes a synthesis of informa- tion from geological investigations of the Opalinus Clay and a report on engineering feasibility.
Presentation to the Nuclear Waste Technical Review Board (NWTRB) in regards to integrating standardization into the nuclear waste management system.
The Centralized Interim Storage Facility (CISF) is designed as a temporary, above-ground away-from-reactor spent fuel storage installation for up to 40,000 metric tons of uranium (MTU). The design is non-site-specific but incorporates conservative environmental and design factors (e.g., 360 mph tornado and 0.75 g seismic loading) intended to be capable of bounding subsequent site-specific factors. Spent fuel is received in dual-purpose canister systems and/or casks already approved for transportation and storage by the Nuclear Regulatory Commission (NRC).
Nuclear Fuels Storage and Transportation Planning Project (NFST) Overview Presentation, 2014 Fuel Cycle Technologies (FCT) Annual Meeting, November 4-6, 2014, Idaho Falls, ID
Slides - Institute of Nuclear Materials Management, 55th Annual Meeting, July 20 – 24, 2014 Atlanta, Georgia
Slides - Institute of Nuclear Materials Management, 55th Annual Meeting, July 20 – 24, 2014 Atlanta, Georgia
The Law of 30 December 1991 [1] confers to Andra the mission of assessing the feasibility of a repository of high-level and long-lived (HLLL) waste in a deep geological formation.
The Committee on Radioactive Waste Management (CoRWM) has carried out an assessment of the generic Disposal System Safety Case (gDSSC) published by the Radioactive Waste Management Directorate (RWMD) of the Nuclear Decommissioning Authority (NDA) in February 2011. The assessment covered the whole suite of gDSSC documents, and related RWMD reports on research and development (R&D) and site characterisation.
