Research on Performance Analysis Methods for Typical Lattice of Heat Pipe Reactors Based on the MOOSE Platform

Qi Min; Li Chenxi; He Yanan; Wang Yanpei; Yang Guangliang; Li Yuanming; Wang Haoyu

doi:10.13832/j.jnpe.2025.S1.0103

Volume 46 Issue S1

Jul. 2025

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Qi Min, Li Chenxi, He Yanan, Wang Yanpei, Yang Guangliang, Li Yuanming, Wang Haoyu. Research on Performance Analysis Methods for Typical Lattice of Heat Pipe Reactors Based on the MOOSE Platform[J]. Nuclear Power Engineering, 2025, 46(S1): 103-112. doi: 10.13832/j.jnpe.2025.S1.0103

Citation:

Qi Min, Li Chenxi, He Yanan, Wang Yanpei, Yang Guangliang, Li Yuanming, Wang Haoyu. Research on Performance Analysis Methods for Typical Lattice of Heat Pipe Reactors Based on the MOOSE Platform[J]. Nuclear Power Engineering, 2025, 46(S1): 103-112. doi: 10.13832/j.jnpe.2025.S1.0103

Citation:

Qi Min, Li Chenxi, He Yanan, Wang Yanpei, Yang Guangliang, Li Yuanming, Wang Haoyu. Research on Performance Analysis Methods for Typical Lattice of Heat Pipe Reactors Based on the MOOSE Platform[J]. Nuclear Power Engineering, 2025, 46(S1): 103-112. doi: 10.13832/j.jnpe.2025.S1.0103

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Research on Performance Analysis Methods for Typical Lattice of Heat Pipe Reactors Based on the MOOSE Platform

doi: 10.13832/j.jnpe.2025.S1.0103

1.
School of Energy and Power Engineering, Xi’an Jiaotong University, Xi’an, 710049, China
2.
National Key Laboratory of Nuclear Reactor Technology, Nuclear Power Institute of China, Chengdu, 610213, China
3.
State Key Laboratory of Multiphase Flow in Power Engineering, Xi’an Jiaotong University, Xi’an, 710049, China

Received Date: 2025-01-15
Rev Recd Date: 2025-05-12
Publish Date: 2025-07-09

Abstract

Abstract

To address the challenge of characterizing the behavior of fuel assemblies at different radial positions in heat pipe reactors, this paper develops a typical fuel assembly code and a MultiApp code based on the MOOSE platform. The typical fuel assembly code enables detailed analysis of fuel assemblies at specific positions, while the MultiApp code is capable of performing full-core calculations. The combination of the two codes ensures consistency and accuracy in calculating the stress, strain, and temperature at different radial positions. The calculation results of the typical fuel assembly code under different boundary conditions indicate that the stress calculation results are overestimated under symmetric boundary conditions, while the stress results under free boundary conditions are more reasonable. The temperature calculations under combined boundaries and periodic boundaries are similar, but the stress results are different. By comparing the typical fuel assembly code with the full-core calculation code, it is found that the typical fuel assembly under free boundary conditions has better capability to represent the thermo-mechanical behavior of the full core under steady-state operation with a uniform power distribution.
- MOOSE platform,
- Fuel element performance,
- Boundary conditions

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References(11)

References

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