Published March 23, 2000
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Thermal Analysis of Cold Vacuum Drying (CVD) of Spent Nuclear Fuel (SNF)
Creators
Description
The thermal analysis examined transient thermal and chemical behavior of the Multi-Canister Overpack (MCO) container for a broad range of cases that represent the Cold Vacuum Drying (CVD) processes. The cases were defined to consider both normal and off-normal operations at the CVD Facility for an MCO with N Reactor spent fuel. This analysis provides the basis for the MCO thermal behavior at the CVD Facility in support of the safety basis documentation
Availability note (English)
Available from INIS in electronic form; Also available from OSTI as DE00801897; PURL: https://www.osti.gov/servlets/purl/801897-jAqVRq/webviewable/Files
34020656.pdf
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Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 212 p.
- Report number
- HNF-SD-SNF-CN--023/Rev.2
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 34020656
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- CONTAINERS; DOCUMENTATION; DRYING; N-REACTOR; NUCLEAR FUELS; SAFETY; SPENT FUELS; THERMAL ANALYSIS; TRANSIENTS
- Descriptors DEC
- ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; GRAPHITE MODERATED REACTORS; LWGR TYPE REACTORS; MATERIALS; NUCLEAR FUELS; PLUTONIUM PRODUCTION REACTORS; POWER REACTORS; PRODUCTION REACTORS; REACTOR MATERIALS; REACTORS; WATER COOLED REACTORS
Optional Information
- Contract/Grant/Project number
- ECN-659300; AC06-96RL13200
- Funding organization
- ENVIRONMENTAL MANAGEMENT (United States)