Published 2002 | Version v1
Book

Modeling of MOX Fuel Pellet-Clad Interaction Using ABAQUS

  • 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