Modeling of MOX Fuel Pellet-Clad Interaction Using ABAQUS
Creators
- 1. INEEL - Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID 83415 (United States)
- 2. Oregon State University, Corvallis, OR 97331-4501 (United States)
Description
Post-irradiation examination (PIE) has indicated an increase in the outer diameter of fuel pins being irradiated in the Advanced Test Reactor (ATR) for the MOX irradiation program. The diameter increase is the largest in the region between fuel pellets. The fuel pellet was modeled using PATRAN and the model was evaluated using ABAQUS, version 6.2. The results from the analysis indicate the non-uniform clad diameter is caused by interaction between the fuel pellet and the clad. The results also demonstrate that the interaction is not uniform over the pellet axial length, with the largest interaction occurring in the region of the pellet-pellet interface. Results were obtained for an axisymmetric model and for a 1/8 pie shaped segment, using the coupled temperature-displacement solution technique. (authors)
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers - ASME
- Imprint Place
- New York (United States)
- Imprint Pagination
- 6 p.
Conference
- Title
- 10. international conference on nuclear engineering
- Acronym
- ICONE-10
- Dates
- 14-18 Apr 2002
- Place
- Arlington - Virginia (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 39079593
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AXIAL SYMMETRY; FUEL PELLETS; FUEL PINS; IRRADIATION; MIXED OXIDE FUELS; POST-IRRADIATION EXAMINATION; SIMULATION; TEST REACTORS
- Descriptors DEC
- ENERGY SOURCES; FUEL ELEMENTS; FUELS; MATERIALS; NUCLEAR FUELS; PELLETS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SOLID FUELS; SYMMETRY; TEST FACILITIES