Analytical Evaluation of Preliminary Drop Tests Performed to Develop a Robust Design for the Standardized DOE Spent Nuclear Fuel Canister

Conference · Sun Aug 01 00:00:00 EDT 1999

OSTI ID:7637

Ware, A G; Morton, D K; Smith, N L; Snow, S D; Rahl, T E

The Department of Energy (DOE) has developed a design concept for a set of standard canisters for the handling, interim storage, transportation, and disposal in the national repository, of DOE spent nuclear fuel (SNF). The standardized DOE SNF canister has to be capable of handling virtually all of the DOE SNF in a variety of potential storage and transportation systems. It must also be acceptable to the repository, based on current and anticipated future requirements. This expected usage mandates a robust design. The canister design has four unique geometries, with lengths of approximately 10 feet or 15 feet, and an outside nominal diameter of 18 inches or 24 inches. The canister has been developed to withstand a drop from 30 feet onto a rigid (flat) surface, sustaining only minor damage - but no rupture - to the pressure (containment) boundary. The majority of the end drop-induced damage is confined to the skirt and lifting/stiffening ring components, which can be removed if de sired after an accidental drop. A canister, with its skirt and stiffening ring removed after an accidental drop, can continue to be used in service with appropriate operational steps being taken. Features of the design concept have been proven through drop testing and finite element analyses of smaller test specimens. Finite element analyses also validated the canister design for drops onto a rigid (flat) surface for a variety of canister orientations at impact, from vertical to 45 degrees off vertical. Actual 30-foot drop testing has also been performed to verify the final design, though limited to just two full-scale test canister drops. In each case, the analytical models accurately predicted the canister response.

• 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: 7637
• Report Number(s): INEEL/CON-99-00136; TRN: US0101802
• Resource Relation: Conference: ASME Pressure Vessel and Piping Conference, Boston, MA (US), 08/01/1999--08/04/1999; Other Information: PBD: 1 Aug 1999
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
SPENT FUEL CASKS
DESIGN
SPENT FUEL STORAGE
PERFORMANCE TESTING
WASTE TRANSPORTATION
IMPACT TESTS
RADIOACTIVE WASTE DISPOSAL
INTERIM STORAGE
TRANSPORTATION
DISPOSAL
NATIONAL REPOSITORY
SPENT NUCLEAR FUEL (SNF)
CANISTER DESIGN
DROP TESTING
FINITE ELEMENT ANALYSES
STANDARD CANISTERS