The prospective usage of the multi-purpose canister and impacts on the waste management and disposal system
Description
The Multi-Purpose Canister (MPC) is designed to be loaded with spent fuel and sealed at reactors and then serve the functions of transport, storage and disposal without reopening. It can be either self-shielded or unshielded, thus requiring compatible overpacks for transport, storage and disposal. The MPC is not a new concept but it may now be viable because of the particular characteristics at Yucca Mountain: larger MPCs are possible because of ramp access to the repository horizon, and the less difficult temperature limits because of in-drift emplacement, rather than borehole emplacement. This paper describes the advantages and disadvantages of adopting the MPC as the principal technology to be employed in the US program. Use of the MPC permits integration of the utility and DOE portions of the system as well as among the elements within the DOE portion. Paradoxically, the principal disadvantage of the MPC is a direct consequence of its merit as an integrating technology. Full integration includes disposability without reopening, and requires that disposability design decisions be made and implemented well in advance of when waste package licensing uncertainties are resolved. There is, therefore, a risk that MPCs loaded prior to waste package licensing will have to be opened. This risk is discussed in terms of probability and consequences and various alternatives for mitigating this risk are discussed
Additional details
Publishing Information
- Publisher
- Institute of Nuclear Materials Management.
- Imprint Place
- Northbrook, IL (United States)
- Imprint Title
- Nuclear materials management. 34th Annual meeting proceedings: Volume 22
- Imprint Pagination
- 1190 p.
- Journal Page Range
- p. 77-82.
Conference
- Title
- 34. annual meeting of the Institute of Nuclear Materials Management.
- Dates
- 18-21 Jul 1993.
- Place
- Scottsdale, AZ (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26066727
- Subject category
- S42: ENGINEERING; S42: ENGINEERING; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPLIANCE; DESIGN; FLEXIBILITY; IMPLEMENTATION; PACKAGING RULES; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVE WASTE FACILITIES; SPENT FUEL CASKS; SPENT FUEL STORAGE; SPENT FUELS; TRANSPORT; UNDERGROUND DISPOSAL; YUCCA MOUNTAIN
- Descriptors DEC
- CASKS; CONTAINERS; ENERGY SOURCES; FUELS; LAWS; MANAGEMENT; MATERIALS; MECHANICAL PROPERTIES; MOUNTAINS; NUCLEAR FACILITIES; NUCLEAR FUELS; REACTOR MATERIALS; REGULATIONS; STORAGE; TENSILE PROPERTIES; WASTE DISPOSAL; WASTE MANAGEMENT
Optional Information
- Secondary number(s)
- CONF-930749--.