Development of a multi-purpose container system for the storage, transport and disposal of PWR spent fuel in the UK - 15466

Conference · Wed Jul 01 00:00:00 EDT 2015

OSTI ID:22824365

Johnson, Mark ^[1]; Tso, Chi-Fung ^[2]; Carr, Neil ^[1]; Izatt, Conrad ^[2]; Asano, Ryoji ^[3]; Fry, Chris; Wright, George ^[4]

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1. Radioactive Waste Management Limited (United Kingdom)
2. Arup, London (United Kingdom)
3. Hitachi Zosen Corporation (Japan)
4. AMEC, Dorchester (United Kingdom)

Radioactive Waste Management Limited (RWM) is a wholly owned subsidiary of UK's Nuclear Decommissioning Authority, and is responsible for implementing UK Government policy on geological disposal of higher activity radioactive waste. An aspect of the generic work programme that underpins the current generic disposal concepts includes the development of the associated disposal containers. To date RWM has focused on the development of a range of disposal container designs that fulfil the requirements for transport and disposal in a Geological Disposal Facility (GDF) for legacy high heat generating wastes, one of which includes legacy Pressurised Water Reactor (PWR) spent nuclear fuel (SF). In line with a number of European countries exploring deep geological disposal, the conceptual disposal container solution developed for this waste type has a capacity of 4 PWR fuel assemblies. Since 2013, the feasibility of developing an alternative higher capacity disposal container design based around the Multi-Purpose Container (MPC) concept has been explored. In general terms, MPCs are containers that are designed to meet requirements for safe containment of radioactive waste during storage, transport and disposal. The fundamental design philosophy of the MPC is that once the waste is packaged in an MPC, it would not need to be handled again. That is, after a period of initial cooling in a fuel pond, the SF could be packaged for long term dry storage and would not require direct handling for its eventual transport to, and disposal in, a GDF. The novel feature of the MPC system design considered is the inclusion of an additional overpack specifically for the final deep geological disposal phase. The conceptual MPC and its associated storage, transfer, transport and thick walled carbon steel disposal overpack have been developed to a conceptual level of design detail to demonstrate concept feasibility, with the final design solution confirming a MPC system with a capacity of 12 PWR SF assembles. This represents the highest capacity PWR MPC system that complies with the mass and rail gauge limits of the UK W6a rail gauge. Such a capacity realises a contents loading three times that of the standard PWR disposal container and presented technical challenges from both a structural performance and thermal perspective; necessitating the need for the inclusion of features to enhance heat transfer from the central fuel assemblies within the MPC and novel lid features on the transport container overpack to maintain structural integrity and containment during the hypothetical accident conditions of transport tests. In developing the MPC system conceptual design it is recognised that, depending upon the safety functions of the MPC disposal overpack, the choice of carbon steel material may not be suitable for all geological environments. Consequently, the MPC system design and its materials of construction will require further evaluation once detailed knowledge of the disposal concept to be implemented, its safety functions and geological environment are known. (authors)

• Research Organization: WM Symposia, Inc., PO Box 27646, 85285-7646 Tempe, AZ (United States)
• OSTI ID: 22824365
• Report Number(s): INIS-US-19-WM-15466; TRN: US19V0937069411
• Resource Relation: Conference: WM2015: Annual Waste Management Symposium, Phoenix, AZ (United States), 15-19 Mar 2015; Other Information: Country of input: France; 9 refs.; available online at: http://archive.wmsym.org/2015/index.html
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CAPACITY
CARBON STEELS
CONTAINMENT
COOLING
DRY STORAGE
ENVIRONMENT
FUEL ASSEMBLIES
FUEL STORAGE POOLS
GOVERNMENT POLICIES
HEAT TRANSFER
HYPOTHETICAL ACCIDENTS
PERFORMANCE
PWR TYPE REACTORS
RADIOACTIVE WASTE MANAGEMENT
REACTOR DECOMMISSIONING
SAFETY
SPENT FUEL CASKS
SPENT FUELS
UNDERGROUND STORAGE
UNITED KINGDOM ORGANIZATIONS
WALLS
WASTE TRANSPORTATION