Update of CSFM Creep and Creep Rupture Models for Determining Temperature Limits for Dry Storage of Spent Fuel
Creators
- 1. Battelle Pacific Northwest Laboratory, Richland, WA (United States)
- 2. Assoc Western University (United States)
Description
Creep rupture is believed to be a dominant mode of cladding failure during dry storage of spent nuclear fuel. This paper describes a methodology to determine the maximum allowable temperature for dry SNF storage based on expected time-in-storage, cooling time after discharge, fuel rod inner pressure, burnup, and material properties of Zircalay cladding. The methodology employs a Monkman-Grant correlation to predict the time-to-rupture as a function of steady-state creep rate. The steady-state creep rate is calculated using different creep mechanisms developed from recently published experimental data. Several creep mechanisms were found to be active during dry SNF storage conditions. The methodology incorporates creep adjustment factors due to irradiation damage and thermal annealing.
Availability note (English)
Available from American Nuclear Society, LaGrange Park, IL (US)Additional details
Publishing Information
- Imprint Pagination
- vp.
- Report number
- PNNL-SA--36236
Conference
- Title
- International Congress on Advanced Nuclear Power Plants (ICAPP) embedded topical meeting
- Dates
- 9-13 Jun 2002
- Place
- Hollywood, FL (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 41105209
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ANNEALING; BURNUP; COOLING TIME; CREEP; DRY STORAGE; FUEL RODS; IRRADIATION; NUCLEAR FUELS; NUCLEAR POWER PLANTS; RUPTURES; SPENT FUELS; STORAGE
- Descriptors DEC
- ENERGY SOURCES; FAILURES; FUEL ELEMENTS; FUELS; HEAT TREATMENTS; MATERIALS; MECHANICAL PROPERTIES; NUCLEAR FACILITIES; NUCLEAR FUELS; POWER PLANTS; REACTOR COMPONENTS; REACTOR MATERIALS; STORAGE; THERMAL POWER PLANTS
Optional Information
- Contract/Grant/Project number
- 401001060; AC06-76RL01830
- Funding organization
- US Department of Energy (United States)