A methodology for the evaluation of fuel rod failures under transportation accidents
Creators
- 1. EPRI, Palo Alto (United States)
- 2. ANATECH, San Diego, CA (United States)
Description
Recent studies on long-term behavior of high-burnup spent fuel have shown that under normal conditions of stor-age, challenges to cladding integrity from various postulated damage mechanisms, such as delayed hydride crack-ing, stress-corrosion cracking and long-term creep, would not lead to any significant safety concerns during dry storage, and regulatory rules have subsequently been established to ensure that a compatible level of safety is maintained. However, similar safety assurances for spent fuel transportation have not yet been developed, and further studies are currently being conducted to evaluate the conditions under which transportation-related safety issues can be resolved. One of the issues presently under evaluation is the ability and the extent of the fuel as-semblies to maintain non-reconfigured geometry during transportation accidents. This evaluation may determine whether, or not, the shielding, confinement, and criticality safety evaluations can be performed assuming initial fuel assembly geometries. The degree to which spent fuel re-configuration could occur during a transportation accident would depend to a large degree on the number of fuel rod failures and the type and geometry of the failure modes. Such information can only be developed analytically, as there is no direct experimental data that can provide guidance on the level of damage that can be expected. To this end, the paper focuses on the development of a modeling and analysis methodology that deals with this general problem on a generic basis. First consideration is given to defining acci-dent loading that is equivalent to the bounding, although analytically intractable, hypothetical transportation acci-dent of a 9-meter drop onto essentially unyielding surface, which is effectively a condition for impact-limiters de-sign. Second, an analytically robust material constitutive model, an essential element in a successful structural analysis, is required. A material behavior model, with embedded failure criteria, for cladding containing various concentrations of circumferentially and radially oriented hydrides has been developed and implemented in a finite element code. The characterization of hydrides-dependent properties of high-burnup fuel cladding is the main fea-ture of this constitutive model. The third element in the overall process is to utilize this material model and its host finite element code in the structural analysis of a transportation cask subjected to bounding accident loading to cal-culate fuel rod failures and failure mode configurations. This requires detailed modeling of the transport cask and its internal structure, which include canister, basket, fuel assembly grids and fuel rods. The overall methodology is described in the paper
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37088728.pdf
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Additional details
Publishing Information
- Imprint Title
- PATRAM 2004 - The 14th international symposium on the packaging and transportation of radioactive materials. Conference proceedings
- Imprint Pagination
- [CD-ROM]
- Journal Page Range
- 8 p.
- Report number
- INIS-DE--0129
Conference
- Title
- 14. international symposium on the packaging and transportation of radioactive materials
- Acronym
- PATRAM 2004
- Dates
- 20-24 Sep 2004
- Place
- Berlin (Germany)
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 37088728
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENTS; BURNUP EXTENSION; COMPUTERIZED SIMULATION; CRITICALITY; FAILURE MODE ANALYSIS; FINITE ELEMENT METHOD; FUEL RODS; FUEL-CLADDING INTERACTIONS; RISK ASSESSMENT; SAFETY ANALYSIS; SPENT FUELS; TRANSPORT
- Descriptors DEC
- BURNUP; CALCULATION METHODS; ENERGY SOURCES; FUEL ELEMENTS; FUELS; MATERIALS; MATHEMATICAL SOLUTIONS; NUCLEAR FUELS; NUMERICAL SOLUTION; REACTOR COMPONENTS; REACTOR MATERIALS; SIMULATION; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS
Optional Information
- Notes
- Paper No. 118