Preliminary Research on a Multi-Physics Coupling Platform for Heat Pipe Reactors

被引：0
作者：
Li X. [1 ]
Xiao W. [1 ]
Zhang T. [1 ]
Li P. [1 ]
Liu X. [1 ]
机构：
[1] School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai
来源：
Hedongli Gongcheng/Nuclear Power Engineering | 2021年 / 42卷 / 02期
关键词：
Heat pipe reactor; KRUSTY; Multi-physics coupling; Numerical simulation; Open-source program;
D O I：
10.13832/j.jnpe.2021.02.0208
中图分类号：
学科分类号：
摘要：
In order to achieve high-precision and high-fidelity numerical simulations of nuclear energy system and to explore the true physical process therein, a coupled three-dimensional high-fidelity calculation platform named MPCH for neutronics/thermal-conduction/stress-analysis calculation has been developed in this work. Therefore, MPCH can be used to perform a series of multi-physics coupled calculation of neutron transport, thermal conduction and thermal expansion. MPCH is constructed based on Picard iteration by integrating open-source codes: OpenMC, Nektar++ and SfePy. In this paper, the new space heat pipe reactor KRUSTY is calculated and analyzed under MPCH. The calculation results of multi-physics coupling show that MPCH can effectively predict the effective multiplication factor change, power distribution, temperature distribution and thermal expansion of the KRUSTY reactor. At the power of 4 kW, the local temperature difference of the whole reactor is 21.6K. The thermal stress leads to the deformation rate of 2.47%. Moreover, the effect of neutronics/thermal-conduction/stress-analysis coupling tends to make a more uniform temperature distribution of the core. This multi-physical coupling calculation program plays an important role in the design, development and verification of new reactors. © 2021, Editorial Board of Journal of Nuclear Power Engineering. All right reserved.
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页码：208 / 212
页数：4
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