Development and application of multi-scale thermal fluid coupling program for molten salt cooled fast reactor based on RELAP5 and sub-channel program

被引：0
|
作者：
Song S. [1 ,2 ]
Cheng M. [1 ,2 ]
Lin M. [1 ]
Dai Z. [1 ,2 ]
机构：
[1] Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai
[2] University of Chinese Academy of Sciences, Beijing
来源：
He Jishu/Nuclear Techniques | 2022年 / 45卷 / 07期
关键词：
Coupling code; Multiscale; Natural circulation chloride-cooled fast reactors; Subchannel; System program;
D O I：
10.11889/j.0253-3219.2022.hjs.45.070602
中图分类号：
学科分类号：
摘要：
[Background] The natural circulation chloride cooled fast reactor (N3CFR) has the characteristics of simple structure, high inherent safety and good economy. It is an advanced fourth-generation nuclear energy system with development potential. However, we are not able to calculate 3D thermal fluids in core when modeled using RELAP5-TMSR. [Purpose] This study aims to improve the applicability and accuracy of the RELAP5-TMSR program in transient analysis and safety assessment of small natural circulation chloride cooled fast reactor (SN3CFR). [Methods] Firstly, the coupling code was developed with an external explicit method, and verified by the horizontal tube model based on the system analysis code RELAP5-TMSR and the sub-channel code ThorSUBTH. Then, according to the natural circulation primary circuit main cooling system, a multiscale model of the SN3CFR was established to evaluate the applicability of the coupled code. Finally, the reactor steady-state operating parameters and the reactivity insertion incident conditions were calculated and analyzed. [Results] The results show that the coupling code is in good agreement with the verification examples, and all key thermal parameters of SN3CFR meet design limits under reactive introduction accident conditions. [Conclusions] The development of a multiscale thermal hydraulics coupling code can perform system analysis fast and calculate the thermal fluid of the core more accurately, which is of great significance for the system design, safety analysis and optimization of molten salt cooled reactors. © 2022 Science Press. All rights reserved.
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