Development and application of three-dimensional multi-physics and multi-scale coupling program for lead cooled fast reactor

被引：0

作者：

Dong, Sifan ^{[1
]}

Wei, Jingguo ^{[1
]}

Wang, Weixiang ^{[1
]}

Zhang, Kefan ^{[1
]}

Pan, Rui ^{[1
]}

Wang, Shuai ^{[1
]}

Chen, Hongli ^{[1
]}

机构：

[1] Univ Sci & Technol China, Sch Nucl Sci & Technol, Hefei 230026, Anhui, Peoples R China

来源：

ANNALS OF NUCLEAR ENERGY | 2025年 / 219卷

基金：

中国国家自然科学基金;

关键词：

Multi-scale; Nuclear thermal coupling; OpenMOC; ICoCo; CODE;

D O I：

10.1016/j.anucene.2025.111486

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

High-fidelity and high-precision nuclear-thermal coupling calculations for reactors can more accurately simulate the core behavior of a reactor. This work investigates the coupling of neutron physics and thermal-hydraulic behavior using the pin-by-pin subchannel thermal-hydraulic simulation code KMC-FBc based on precise geometric modeling and high-accuracy MOC (Method of Characteristics) neutron transport calculations. To examine the transient characteristics of natural circulation lead-bismuth fast reactors, this work integrates the system code RELAP5 and develops the OpenMOC/KMC-FBc/RELAP5. And the correctness of the coupling program is proved by comparing the calculation results of RELAP5. In this paper, the OpenMOC/KMC-FBc/RELAP5 coupling program is used to simulate the thermal and hydraulic phenomena under the steady state and accident conditions of the natural circulation lead cooled fast reactor (SNCLFR-100) designed by the University of Science and Technology of China. The accident conditions include unprotected transient overpower accident and unprotected loss of heat-sink accident. The results show that the OpenMOC/KMC-FBc/RELAP5 provides high accuracy and can effectively capture the physical and thermal-hydraulic variations in the reactor core under transient conditions.

引用

页数：14

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