MULTI-PHYSICS COUPLING SIMULATION OF A SMALL FLOATING LEAD-COOLED FAST REACTOR BASED ON OPENMC AND GEN-FOAM

被引:0
作者
Huang, Haochen [1 ]
Xie, Fei [1 ]
Liu, Yu [1 ,2 ]
Lu, Daogang [1 ,2 ]
机构
[1] North China Elect Power Univ, Sch Nucl Sci & Engn, Beijing 102206, Peoples R China
[2] North China Elect Power Univ, Beijing Key Lab Pass Safety Technol Nucl Energy, Beijing 102206, Peoples R China
来源
PROCEEDINGS OF 2024 31ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 10, ICONE31 2024 | 2024年
关键词
Small floating lead-cooled fast reactor; multi-physics coupling; OpenMC; GeN-Foam;
D O I
暂无
中图分类号
TE [石油、天然气工业]; TK [能源与动力工程];
学科分类号
0807 ; 0820 ;
摘要
The small modular floating lead-cooled fast reactor represents a typical fourth-generation reactor, featuring advantages such as compact structure, flexible layout, and inherent safety, making it suitable for providing power to oceanic islands and remote areas, and thus, is of significant importance for global energy security. This paper focuses on a 50MWth fully natural circulation small modular floating lead-cooled fast reactor, and conducts research on the multi-physics coupling of the reactor. Firstly, utilizing the OpenMC program, simplified model of the small lead-cooled fast reactor is established for simulation and calculation of the reactor's cross-section parameters, which will serve as input parameters for the GeN-Foam program. Subsequently, a full-core three-dimensional multi-physics field coupling model encompassing neutron physics, thermal-hydraulic, and structural mechanics is established using the GeN-Foam program. The model is fed with the cross-sectional parameters calculated by the OpenMC program and other relevant core parameters, and steady-state operational numerical simulation is conducted, yielding positive findings for parameters like core outlet temperature and maximum fuel temperature. Finally, simulations of transient emergency reactor shutdown scenarios are performed, obtaining the changing patterns of operational parameters such as coolant temperature distribution, core power density distribution, and fuel rod deformation with respect to control rod position and power level. This paper plays a significant role in the design and operation of small lead-cooled fast reactors.
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页数:8
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