TY - JOUR
T1 - Neutronics/thermal-hydraulics/fuel-performance coupling for light water reactors and its application to accident tolerant fuel
AU - Xu, Xiaobei
AU - Liu, Zhouyu
AU - Wu, Hongchun
AU - Cao, Liangzhi
N1 - Publisher Copyright:
© 2021 Elsevier Ltd
PY - 2022/2
Y1 - 2022/2
N2 - To accurately assess the in-pile performance of the accident tolerant fuel (ATF) over the whole life for the light water reactors (LWR), a full coupling of neutronics/thermal-hydraulics/fuel-performance is needed. In this paper, a multiphysics coupling code system named NECP-CLAMPERL is developed based on the high-fidelity neutronics code NECP-X, the sub-channel thermal-hydraulics code CTF, the finite-element fuel performance code NECP-CALF and the multiphysics object-oriented simulation environment (MOOSE). The code system is then applied to evaluate the performance of U3Si2 fuel, one of the most promising ATFs, by simulating a typical fuel assembly in pressurized water-cooled reactors (PWR). The quantities of interest including the reactivity, power distribution, fuel temperature, clad stress, fission gas release, plenum pressure, fuel radial displacement, gap width and PCMI are presented and analyzed in comparison with the traditional UO2 fuel. Future works and other potential applications are also identified.
AB - To accurately assess the in-pile performance of the accident tolerant fuel (ATF) over the whole life for the light water reactors (LWR), a full coupling of neutronics/thermal-hydraulics/fuel-performance is needed. In this paper, a multiphysics coupling code system named NECP-CLAMPERL is developed based on the high-fidelity neutronics code NECP-X, the sub-channel thermal-hydraulics code CTF, the finite-element fuel performance code NECP-CALF and the multiphysics object-oriented simulation environment (MOOSE). The code system is then applied to evaluate the performance of U3Si2 fuel, one of the most promising ATFs, by simulating a typical fuel assembly in pressurized water-cooled reactors (PWR). The quantities of interest including the reactivity, power distribution, fuel temperature, clad stress, fission gas release, plenum pressure, fuel radial displacement, gap width and PCMI are presented and analyzed in comparison with the traditional UO2 fuel. Future works and other potential applications are also identified.
KW - ATF
KW - MOOSE
KW - Multiphysics coupling
KW - NECP-X
KW - USi
UR - https://www.scopus.com/pages/publications/85119187999
U2 - 10.1016/j.anucene.2021.108809
DO - 10.1016/j.anucene.2021.108809
M3 - 文章
AN - SCOPUS:85119187999
SN - 0306-4549
VL - 166
JO - Annals of Nuclear Energy
JF - Annals of Nuclear Energy
M1 - 108809
ER -