A probabilistic assessment of PWR SNF pinching failure considering hydride-related cladding embrittlement
- 1. University of Utah, Civil & Environmental Engineering, 110 S. Central Campus Drive, Suite 2000, Salt Lake City, UT 84112 (United States)
- 2. Simpson Gumpertz & Heger, 41 Seyon Street, Building 1, Suite 500, Waltham, MA 02453 (United States)
Description
Highlights: • The probability of pinching failure does not exceed 0.2%. • Only highly embrittled cladding fails. • Radial hydride embrittlement controls hydride-related embrittlement. • The diametric cladding deformations are small. - Abstract: A probabilistic methodology to investigate pinching failure of pressurized water reactor (PWR) spent nuclear fuel (SNF) rod cladding is presented. The considered accident scenario is a 9-m SNF transportation cask drop after long-term SNF dry storage. The offset strain was used to evaluate cladding failure. A set of 3000 pinching scenarios was generated via Latin Hypercube Sampling (LHS) of geometrical, material, and loading parameters and finite element (FE) models were developed to simulate each scenario. The methodology considers hydride-related cladding embrittlement related to SNF dry storage cool-down. Regression and interpolation models were developed to estimate the cladding offset strain capacity as a function of cladding hydrogen content, peak vacuum drying cladding hoop stress, and cladding temperature at the moment of load application. The probabilistic results indicate a small likelihood of hydride-related pinching failure in the considered accident scenario, after 30 or 300 years of SNF dry storage.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2019.05.024Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2019.05.024;
- PII
- S0029549319301360;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 351
- Journal Page Range
- p. 116-130
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51056248
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- CLADDING; DRY STORAGE; EMBRITTLEMENT; FAILURES; FINITE ELEMENT METHOD; FUEL RODS; HYDRIDES; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; SPENT FUELS; TEMPERATURE MONITORING
- Descriptors DEC
- CALCULATION METHODS; DEPOSITION; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; FUELS; HYDROGEN COMPOUNDS; MATERIALS; MATHEMATICAL SOLUTIONS; MONITORING; NUCLEAR FUELS; NUMERICAL SOLUTION; POWER REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; STORAGE; SURFACE COATING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- © 2019 Elsevier B.V. All rights reserved.