TY - GEN
T1 - Development of Fuel Performance Analysis Code for Liquid Metal Coole Fast Reactor Based on MOOSE Platform
AU - Shao, Shihao
AU - Liu, Zhouyu
AU - Xu, Xiaobei
AU - Zong, Yufan
AU - Cao, Liangzhi
AU - Wu, Hongchun
N1 - Publisher Copyright:
© The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd 2024.
PY - 2024
Y1 - 2024
N2 - The liquid metal cooled fast reactor is of great strategic significance for the innovative development of nuclear energy in China, and the development of fuel performance analysis programs suitable for it is of great significance for the design and safety analysis of fast reactors. This article is based on the multi physics coupling platform MOOSE and finite element method, and independently developed the fuel performance analysis program LoongCALF for liquid metal cooled fast reactors. The program adopts a 1.5-dimensional modeling method to perform multi-physical field coupling calculations on the fuel rods, which uses a single-layer thermal-mechanical module and a global gas behavior module. The program is suitable for fast reactor fuel elements with MOX and HT-9 cladding. For the calculation example of a complete fuel rod whose pellet material is MOX and cladding material is HT-9, LoongCALF program and China Institute of Atomic Energy program are respectively used to model and calculate the calculation example, and the calculation results are compared. The results indicate that the LoongCALF program can accurately simulate the spatial distribution and temporal variation of key physical parameters inside fuel elements under steady-state operating conditions of liquid metal cooled fast reactors.
AB - The liquid metal cooled fast reactor is of great strategic significance for the innovative development of nuclear energy in China, and the development of fuel performance analysis programs suitable for it is of great significance for the design and safety analysis of fast reactors. This article is based on the multi physics coupling platform MOOSE and finite element method, and independently developed the fuel performance analysis program LoongCALF for liquid metal cooled fast reactors. The program adopts a 1.5-dimensional modeling method to perform multi-physical field coupling calculations on the fuel rods, which uses a single-layer thermal-mechanical module and a global gas behavior module. The program is suitable for fast reactor fuel elements with MOX and HT-9 cladding. For the calculation example of a complete fuel rod whose pellet material is MOX and cladding material is HT-9, LoongCALF program and China Institute of Atomic Energy program are respectively used to model and calculate the calculation example, and the calculation results are compared. The results indicate that the LoongCALF program can accurately simulate the spatial distribution and temporal variation of key physical parameters inside fuel elements under steady-state operating conditions of liquid metal cooled fast reactors.
KW - Finite element method
KW - Fuel performance analysis
KW - Liquid metal cooled fast reactor
KW - MOOSE
UR - https://www.scopus.com/pages/publications/85180537691
U2 - 10.1007/978-981-99-7157-2_27
DO - 10.1007/978-981-99-7157-2_27
M3 - 会议稿件
AN - SCOPUS:85180537691
SN - 9789819971565
T3 - Springer Proceedings in Physics
SP - 261
EP - 270
BT - Proceedings of the 2023 Water Reactor Fuel Performance Meeting - WRFPM 2023
A2 - Liu, Jianqiao
A2 - Jiao, Yongjun
PB - Springer Science and Business Media Deutschland GmbH
T2 - International Conference on Water Reactor Fuel Performance Meeting, WRFPM 2023
Y2 - 17 July 2023 through 21 July 2023
ER -