Cermet Spent Nuclear Fuel Casks and Waste Packages
Creators
- 1. Nuclear Science and Technology Division, Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN, 37831-6165 (United States)
Description
Multipurpose transport, aging, and disposal casks are needed for the management of spent nuclear fuel (SNF). Self-shielded cermet casks can out-perform current SNF casks because of the superior properties of cermets, which consist of encapsulated hard ceramic particulates dispersed in a continuous ductile metal matrix to produce a strong high-integrity, high-thermal conductivity cask. A multi-year, multinational development and testing program has been developing cermet SNF casks made of steel, depleted uranium dioxide, and other materials. Because cermets are the traditional material of construction for armor, cermet casks can provide superior protection against assault. For disposal, cermet waste packages (WPs) with appropriate metals and ceramics can buffer the local geochemical environment to (1) slow degradation of SNF, (2) reduce water flow though the degraded WP, (3) sorb neptunium and other radionuclides that determine the ultimate radiation dose to the public from the repository, and (4) contribute to long-term nuclear criticality control. Finally, new cermet cask fabrication methods have been partly developed to manufacture the casks with the appropriate properties. The results of this work are summarized with references to the detailed reports. (authors)
Additional details
Publishing Information
- Publisher
- Materials Research Society - MRS
- Imprint Place
- Warrendale (United States)
- ISBN
- 978-1-55899-942-8
- Imprint Title
- Proceedings of the symposium on Scientific Basis for Nuclear Waste Management XXX
- Imprint Pagination
- v. 985, 663 p.
- Journal Page Range
- p. 281-286
- CODEN
- MRSPDH
Conference
- Title
- Symposium on Scientific Basis for Nuclear Waste Management
- Dates
- 27 Nov - 1 Dec 2006
- Place
- Boston - Massachusetts (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 39077234
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CASKS; CERAMICS; CERMETS; CRITICALITY; DEPLETED URANIUM; GEOCHEMISTRY; NEPTUNIUM; PARTICULATES; RADIATION DOSES; RADIOACTIVE WASTES; SPENT FUELS; STEELS; THERMAL CONDUCTIVITY
- Descriptors DEC
- ACTINIDES; ALLOYS; CARBON ADDITIONS; CHEMISTRY; COMPOSITE MATERIALS; CONTAINERS; DOSES; ELEMENTS; ENERGY SOURCES; FUELS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; METALS; NUCLEAR FUELS; PARTICLES; PHYSICAL PROPERTIES; RADIOACTIVE MATERIALS; REACTOR MATERIALS; THERMODYNAMIC PROPERTIES; TRANSITION ELEMENT ALLOYS; TRANSURANIUM ELEMENTS; URANIUM; WASTES
Optional Information
- Notes
- 19 refs.