TY - GEN
T1 - Framework for simulation of Pellet/Cladding Thermal Interaction (PCTI) for fuel performance calculations
AU - Hansen, G.
AU - Martineau, R.
AU - Newman, C.
AU - Gaston, D.
PY - 2009
Y1 - 2009
N2 - The accurate modeling of heat transfer across the gap between reactor fuel pellets and the protective cladding is essential to understanding fuel performance, cladding stress and behavior under extended burnup situations. The gap heat transfer impacts both the steady state power that a fuel can support and the transient temperature of the fuel during power excursions. Further, interaction between the heat transfer and pellet mechanics drive the geometry of pellet/cladding mechanical interaction, which influences the stress state in and thus the life of the cladding. This study presents a multidimensional approach for modeling the gap during a simulation where there can be significant motion between the pellet and cladding. A Jacobian-free Newton Krylov method is used to provide for fully-coupled solution of the coupled thermal contact and heat equations.
AB - The accurate modeling of heat transfer across the gap between reactor fuel pellets and the protective cladding is essential to understanding fuel performance, cladding stress and behavior under extended burnup situations. The gap heat transfer impacts both the steady state power that a fuel can support and the transient temperature of the fuel during power excursions. Further, interaction between the heat transfer and pellet mechanics drive the geometry of pellet/cladding mechanical interaction, which influences the stress state in and thus the life of the cladding. This study presents a multidimensional approach for modeling the gap during a simulation where there can be significant motion between the pellet and cladding. A Jacobian-free Newton Krylov method is used to provide for fully-coupled solution of the coupled thermal contact and heat equations.
KW - Dissimilar mesh interfaces
KW - Mortar method
KW - Pellet cladding interaction
KW - Reactor fuel performance
UR - https://www.scopus.com/pages/publications/74549142905
M3 - Conference contribution
AN - SCOPUS:74549142905
SN - 9781615673490
T3 - American Nuclear Society - International Conference on Mathematics, Computational Methods and Reactor Physics 2009, M and C 2009
SP - 246
EP - 255
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 -