A High Integrity Can Design for Degraded Nuclear Fuel
A high integrity can (HIC), designed to meet the ASME Boiler and Pressure Vessel Code (Section III, Div. 3, static conditions) is proposed for the interim storage and repository disposal of Department of Energy (DOE) spent nuclear fuel. The HIC will be approximately 5 3/8 inches (134.38mm) in outside diameter with 1/4 inch (6.35mm) thick walls, and have a removable lid with a metallic seal that is capable of being welded shut. The opening of the can is approximately 4 3/8 inches (111.13mm). The HIC is primarily designed to contain items in the DOE SNF inventory that do not meet acceptance standards for direct disposal in a geologic repository. This includes fuel in the form of particulate dusts, sectioned pieces of fuel, core rubble, melted or degraded (non-intact) fuel elements, unclad uranium alloys, metallurgical specimens, and chemically reactive fuel components. The HIC is intended to act as a substitute cladding for the spent nuclear fuel, further isolate problematic materials, provide a long-term corrosion barrier, and add an extra internal pressure barrier to the waste package. The HIC will also delay potential fission product release and maintain geometry control for extended periods of time. For the entire disposal package to be licensed by the Nuclear Regulatory Commission, a HIC must effectively eliminate the disposal problems associated with problem SNF including the release of radioactive and/or reactive material and over pressurization of the HIC due to chemical reactions within the can. Two HICs were analyzed to envelop a range of can lengths between 42 and 101 inches. Using Abacus software, the HIC's were analyzed for end, side, and corner drops. Hastelloy C-22 was chosen based upon structural integrity, corrosion resistance, and neutron adsorption properties.
- Research Organization:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE Office of Environmental Management (EM) (US)
- DOE Contract Number:
- AC07-94ID13223
- OSTI ID:
- 8288
- Report Number(s):
- INEEL/CON-99-00413; TRN: US0101960
- Resource Relation:
- Conference: 1999 ASME Pressure Vessels and Piping Conference, Boston, MA (US), 08/01/1999--08/05/1999; Other Information: PBD: 1 Aug 1999
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
SPENT FUEL CASKS
DESIGN
CORROSION RESISTANCE
URANIUM ALLOYS
RADIOACTIVE WASTE STORAGE
RADIOACTIVE WASTE DISPOSAL
IMPACT TESTS
HASTELLOYS
HIGH INTEGRITY CAN
INTERIM STORAGE
REPOSITORY DISPOSAL
SPENT NUCLEAR FUEL
GEOLOGIC REPOSITORY
CORROSION BARRIER
INTERNAL PRESSURE BARRIER
WASTE PACKAGE
FISSION PRODUCT RELEASE
ABACUS SOFTWARE