A Preliminary Overview of Metal Fuel Models in BISON

Journal Article · Wed Jun 15 00:00:00 EDT 2016 · Transactions of the American Nuclear Society

OSTI ID:22992128

Novascone, S. R.; Medvedev, P. G.; Gamble, K. A.; Gardner, R. J.; Zabriskie, A. X. ^[1]

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1. Fuel Modeling and Simulation, Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415-3840 (United States)

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)

• OSTI ID: 22992128
• Journal Information: Transactions of the American Nuclear Society, Vol. 114, Issue 1; Conference: Annual Meeting of the American Nuclear Society. Embedded topical meeting 'Nuclear fuels and structural material for the next generation nuclear reactors', New Orleans, LA (United States), 12-16 Jun 2016; Other Information: Country of input: France; 20 refs.; Available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 United States; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
36 MATERIALS SCIENCE
97 MATHEMATICAL METHODS AND COMPUTING
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