Multi-scale Coupling Transient Characteristics of Xi 'an Pulsed Reactor Based on RELAP5 and CTF

Zhao Wei; Chen Lixin; Liu Guodong; Zhang Liang; Yang Ning; Zhang Xinyi; Tian Xiaoyan; Sun Peiwei; Yuan Jianxin

doi:10.13832/j.jnpe.2023.03.0059

Volume 44 Issue 3

Jun. 2023

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Article Navigation > Nuclear Power Engineering > 2023 > 44(3): 59-64

Zhao Wei, Chen Lixin, Liu Guodong, Zhang Liang, Yang Ning, Zhang Xinyi, Tian Xiaoyan, Sun Peiwei, Yuan Jianxin. Multi-scale Coupling Transient Characteristics of Xi 'an Pulsed Reactor Based on RELAP5 and CTF[J]. Nuclear Power Engineering, 2023, 44(3): 59-64. doi: 10.13832/j.jnpe.2023.03.0059

Citation:

Zhao Wei, Chen Lixin, Liu Guodong, Zhang Liang, Yang Ning, Zhang Xinyi, Tian Xiaoyan, Sun Peiwei, Yuan Jianxin. Multi-scale Coupling Transient Characteristics of Xi 'an Pulsed Reactor Based on RELAP5 and CTF[J]. Nuclear Power Engineering, 2023, 44(3): 59-64. doi: 10.13832/j.jnpe.2023.03.0059

Citation:

Zhao Wei, Chen Lixin, Liu Guodong, Zhang Liang, Yang Ning, Zhang Xinyi, Tian Xiaoyan, Sun Peiwei, Yuan Jianxin. Multi-scale Coupling Transient Characteristics of Xi 'an Pulsed Reactor Based on RELAP5 and CTF[J]. Nuclear Power Engineering, 2023, 44(3): 59-64. doi: 10.13832/j.jnpe.2023.03.0059

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Multi-scale Coupling Transient Characteristics of Xi 'an Pulsed Reactor Based on RELAP5 and CTF

doi: 10.13832/j.jnpe.2023.03.0059

1.
State Key Laboratory of Intense Pulsed Radiation Simulation and Effect (Northwest Institute of Nuclear Technology), Xi’an, 710024, China
2.
Department of Engineering Physics, Tsinghua University, Beijing, 100084, China
3.
School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, 710049, China

Received Date: 2022-07-21
Rev Recd Date: 2022-10-08
Publish Date: 2023-06-15

Abstract

Abstract

Based on the system code RELAP5 and the sub-channel code CTF, a multi-scale coupling domain decomposition approach for pool pulsed reactor with natural circulation and a grid mapping method that meets the precise conversion between different scale parameters are proposed in this paper. The correctness and feasibility of the coupling method are verified by the analysis of the steady state and transient conditions of the pulsed reactor. The results show that the proposed multi-scale coupling method can be applied to the coupling analysis of the pulsed reactor. The results of coupling calculation are better than those of single system code in accuracy. The accuracy of the fule core temperature is in creased by approximately 62.50% in the 2 MW steady-statecondition and 76,71% under the pulsed transient condition. Meanwhile, the high-precision and high-resolution thermal-hydraulic distribution and transient characteristics of the core can be obtained by coupling calculation.
- Pulsed reactor,
- Domain decomposition approach,
- Multi-scale coupling,
- RELAP5,
- CTF

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References(12)

References

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