Analysis of Dry Storage Temperature Limits for Zircaloy-Clad Spent Nuclear Fuel
Description
Safe interim dry storage of spent nuclear fuel (SNF) must be maintained for a minimum of twenty years according to the Code of Federal Regulations. The most important variable that must be regulated by dry storage licensees in order to meet current safety standards is the temperature of the SNF. The two currently accepted models to define the maximum allowable initial storage temperature for SNF are based on the diffusion controlled cavity growth (DCCG) failure mechanism proposed by Raj and Ashby. These models may not give conservative temperature limits. Some have suggested using a strain-based failure model to predict the maximum allowable temperatures, but we have shown that this is not applicable to the SNF as long as DCCG is the assumed failure mechanism. Although the two accepted models are based on the same fundamental failure theory (DCCG), the researchers who developed the models made different assumptions, including selection of some of the most critical variables in the DCCG failure equation. These inconsistencies are discussed together with recommended modifications to the failure models based on more recent data
Availability note (English)
Available from PURL: https://www.osti.gov/servlets/purl/791267-CLzWNa/native/Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 693 Kilobytes
- Report number
- UCRL-JC--131098
Conference
- Title
- Material Research Society Fall 1999 Meeting
- Dates
- 29 Nov - 3 Dec 1999
- Place
- Boston, MA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 36056261
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- DIFFUSION; DRY STORAGE; MODIFICATIONS; NUCLEAR FUELS; REGULATIONS; SAFETY STANDARDS; STORAGE
- Descriptors DEC
- ENERGY SOURCES; FUELS; LAWS; MATERIALS; REACTOR MATERIALS; STANDARDS; STORAGE
Optional Information
- Contract/Grant/Project number
- W--7405-Eng-48
- Funding organization
- USDOE Office of Defense Programs DP (United States)