A Preliminary Overview of Metal Fuel Models in BISON
- 1. Fuel Modeling and Simulation, Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415-3840 (United States)
Description
BISON is a modern nuclear fuel performance code that has been under development at Idaho National Laboratory (INL) since 2009. It is a finite element-based code capable of solving the energy, mechanics, and species diffusion equations in a fully-coupled sense. BISON also utilizes thermal and mechanical contact algorithms and variety of nonlinear material models. BISON is applicable to steady and transient fuel behavior and supports the use of one-, two-, and three-dimensional meshes. Although thus far used primarily to simulate light water reactor fuel, BISON is designed to be a multi-fuels code. As such, BISON has been used to analyze TRISO-coated particle fuel and metal fuel in rod and plate form, design and interpret fuel irradiation experiments and investigate novel fuel concepts. This publication provides a preliminary list of metal fuel-related material models recently implemented in BISON. Some preliminary results from a simulation of the EBR-II X447 experiment are shown, which begins to demonstrate how all these models work together. A follow-up publication will be presented with more detail at the ANS meeting in New Orleans during the embedded topical meeting titled 'Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors'. (authors)
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 114
- Journal Issue
- 1
- Journal Page Range
- p. 1183-1184
- ISSN
- 0003-018X
Conference
- Title
- Annual Meeting of the American Nuclear Society. Embedded topical meeting 'Nuclear fuels and structural material for the next generation nuclear reactors'
- Dates
- 12-16 Jun 2016
- Place
- New Orleans, LA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52032373
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S36: MATERIALS SCIENCE; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BUILDING MATERIALS; DESIGN; DIFFUSION EQUATIONS; EBR-2 REACTOR; FINITE ELEMENT METHOD; FUEL PARTICLES; IRRADIATION; NUCLEAR FUELS; SIMULATION; THREE-DIMENSIONAL LATTICES; WATER COOLED REACTORS; WATER MODERATED REACTORS
- Descriptors DEC
- BREEDER REACTORS; CALCULATION METHODS; CRYSTAL LATTICES; CRYSTAL STRUCTURE; DIFFERENTIAL EQUATIONS; ENERGY SOURCES; EPITHERMAL REACTORS; EQUATIONS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUELS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS; MATHEMATICAL SOLUTIONS; NUMERICAL SOLUTION; PARTIAL DIFFERENTIAL EQUATIONS; POWER REACTORS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SODIUM COOLED REACTORS
Optional Information
- Notes
- 20 refs.; Available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 United States