TY - BOOK
T1 - BISON theory manual the equations behind nuclear fuel analysis
AU - Hales, Jason D
AU - Williamson, Richard L
AU - Novascone, Stephen R
AU - Pastore, Giovanni
AU - Spencer, Benjamin W
AU - Stafford, DS
AU - Gamble, Kyle A
AU - Perez, Danielle M
AU - Liu, W
PY - 2016/9
Y1 - 2016/9
N2 - BISON is a finite element-based nuclear fuel performance code applicable to a variety of fuel forms including light water reactor fuel rods, TRISO particle fuel, and metallic rod and plate fuel. It solves the fully-coupled equations of thermomechanics and species diffusion, for either 2D axisymmetric or 3D geometries. Fuel models are included to describe temperature and burnup dependent thermal properties, fission product swelling, densification, thermal and irradiation creep, fracture, and fission gas production and release. Plasticity, irradiation growth, and thermal and irradiation creep models are implemented for clad materials. Models are also available to simulate gap heat transfer, mechanical contact, and the evolution of the gap/plenum pressure with plenum volume, gas temperature, and fission gas addition. BISON is based on the MOOSE framework and can therefore efficiently solve problems using standard workstations or very large high-performance computers. This document describes the theoretical and numerical foundations of BISON.
AB - BISON is a finite element-based nuclear fuel performance code applicable to a variety of fuel forms including light water reactor fuel rods, TRISO particle fuel, and metallic rod and plate fuel. It solves the fully-coupled equations of thermomechanics and species diffusion, for either 2D axisymmetric or 3D geometries. Fuel models are included to describe temperature and burnup dependent thermal properties, fission product swelling, densification, thermal and irradiation creep, fracture, and fission gas production and release. Plasticity, irradiation growth, and thermal and irradiation creep models are implemented for clad materials. Models are also available to simulate gap heat transfer, mechanical contact, and the evolution of the gap/plenum pressure with plenum volume, gas temperature, and fission gas addition. BISON is based on the MOOSE framework and can therefore efficiently solve problems using standard workstations or very large high-performance computers. This document describes the theoretical and numerical foundations of BISON.
KW - BISON
KW - Nuclear fuel performance analysis
UR - https://www.osti.gov/biblio/1374503
U2 - 10.2172/1374503
DO - 10.2172/1374503
M3 - Technical Report
T3 - Fuels Modeling Simulation Department, Idaho National Laboratory, Idaho Falls, Idaho
BT - BISON theory manual the equations behind nuclear fuel analysis
ER -