Multi-pack Disposal Concepts for Spent Fuel (Rev. 0)
Creators
- 1. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Description
At the initiation of the Used Fuel Disposition (UFD) R&D campaign, international geologic disposal programs and past work in the U.S. were surveyed to identify viable disposal concepts for crystalline, clay/shale, and salt host media (Hardin et al., 2012). Concepts for disposal of commercial spent nuclear fuel (SNF) and high-level waste (HLW) from reprocessing are relatively advanced in countries such as Finland, France, and Sweden. The UFD work quickly showed that these international concepts are all 'enclosed', whereby waste packages are emplaced in direct or close contact with natural or engineered materials . Alternative 'open' modes (emplacement tunnels are kept open after emplacement for extended ventilation) have been limited to the Yucca Mountain License Application Design (CRWMS M&O, 1999). Thermal analysis showed that, if 'enclosed' concepts are constrained by peak package/buffer temperature, waste package capacity is limited to 4 PWR assemblies (or 9-BWR) in all media except salt. This information motivated separate studies: 1) extend the peak temperature tolerance of backfill materials, which is ongoing; and 2) develop small canisters (up to 4-PWR size) that can be grouped in larger multi-pack units for convenience of storage, transportation, and possibly disposal (should the disposal concept permit larger packages). A recent result from the second line of investigation is the Task Order 18 report: Generic Design for Small Standardized Transportation, Aging and Disposal Canister Systems (EnergySolution, 2015). This report identifies disposal concepts for the small canisters (4-PWR size) drawing heavily on previous work, and for the multi-pack (16-PWR or 36-BWR).
Availability note (English)
Available from http://prod.sandia.gov/sand_doc/2015/1511132r.pdf; PURL: http://www.osti.gov/servlets/purl/1233570/Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 25 p.
- Report number
- SAND--2015-11132R
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 47040110
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- AGING; BWR TYPE REACTORS; CAPACITY; CLAYS; CONTAINERS; DESIGN; HIGH-LEVEL RADIOACTIVE WASTES; PWR TYPE REACTORS; RADIOACTIVE WASTE DISPOSAL; SALTS; SHALES; SPENT FUEL STORAGE; SPENT FUELS; THERMAL ANALYSIS; UNDERGROUND DISPOSAL
- Descriptors DEC
- ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MANAGEMENT; MATERIALS; MINERALS; NUCLEAR FUELS; POWER REACTORS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTE MANAGEMENT; RADIOACTIVE WASTES; REACTOR MATERIALS; REACTORS; ROCKS; SEDIMENTARY ROCKS; SILICATE MINERALS; STORAGE; THERMAL REACTORS; WASTE DISPOSAL; WASTE MANAGEMENT; WASTES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- AC04-94AL85000
- Funding organization
- USDOE Office of Nuclear Energy, Fuel Cycle Technologies (NE-5) (United States)
- Secondary number(s)
- OSTIID--1233570