TY - GEN
T1 - Computational foundations for reactor fuel performance modeling
AU - Newman, C.
AU - Gaston, D.
AU - Hansen, G.
N1 - Funding Information:
Received 21 May 2003; accepted 5 October 2003. The authors acknowledge the support from the National Petroleum Agency (ANP) and the National Council of Scientific and Technological Development (CNPq) for this work. Address correspondence to M. A. Vaz, Ocean Engineering Department, Graduate School of Engineering, Federal University of Rio de Janeiro, P.O Box 60508, Rio de Janeiro 21945-970, Brazil.
PY - 2009
Y1 - 2009
N2 - The simulation of nuclear reactor fuel performance involves complex thermo-mechanical processes between fuel pellets, made of fissile material, and the protective cladding barrier that surrounds the pellets. This paper examines various mathematical and computational issues that impact the thermo-mechanical response of reactor fuel, and are thus important to the development of INL's fuel performance analysis code, BISON. The code employs advanced methods for solving coupled partial differential equation systems that describe multidimensional fuel thermomechanics, heat generation and transport within the fuel, chemical constituent and fuel structural degradation. BISON is designed for fully coupled, steady and transient analysis, and to be efficient on both desktop computers and in massively parallel environments. It employs physics-based preconditioned Jacobian-free Newton-Krylov solution methods and is developed using modern software engineering principles to form a robust, extensible software architecture to provide a predictive capability for fuel performance analysis.
AB - The simulation of nuclear reactor fuel performance involves complex thermo-mechanical processes between fuel pellets, made of fissile material, and the protective cladding barrier that surrounds the pellets. This paper examines various mathematical and computational issues that impact the thermo-mechanical response of reactor fuel, and are thus important to the development of INL's fuel performance analysis code, BISON. The code employs advanced methods for solving coupled partial differential equation systems that describe multidimensional fuel thermomechanics, heat generation and transport within the fuel, chemical constituent and fuel structural degradation. BISON is designed for fully coupled, steady and transient analysis, and to be efficient on both desktop computers and in massively parallel environments. It employs physics-based preconditioned Jacobian-free Newton-Krylov solution methods and is developed using modern software engineering principles to form a robust, extensible software architecture to provide a predictive capability for fuel performance analysis.
KW - Elasticity
KW - Finite elements
KW - Multiphysics
KW - Nuclear fuels
KW - Thermodynamics
UR - https://www.scopus.com/pages/publications/76749135863
M3 - Conference contribution
AN - SCOPUS:76749135863
SN - 9781615673490
T3 - American Nuclear Society - International Conference on Mathematics, Computational Methods and Reactor Physics 2009, M and C 2009
SP - 902
EP - 912
BT - American Nuclear Society - International Conference on Mathematics, Computational Methods and Reactor Physics 2009, M and C 2009
T2 - International Conference on Mathematics, Computational Methods and Reactor Physics 2009, M and C 2009
Y2 - 3 May 2009 through 7 May 2009
ER -