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.
引用
收藏
页数:8
相关论文
共 50 条
  • [21] Multi-physics code coupling methodology for the simulation of accidental transients in sodium cooled fast reactors
    Billo, Georis
    Li, Simon
    Velardo, Heloise
    ANNALS OF NUCLEAR ENERGY, 2024, 202
  • [22] Multi-physics coupling simulation of small mobile nuclear reactor with finite element-based models
    Li, Xiangyue
    Liu, Xiaojing
    Chai, Xiang
    He, Hui
    Zhang, Bin
    Zhang, Tengfei
    COMPUTER PHYSICS COMMUNICATIONS, 2023, 293
  • [23] Development and application of CFD and subchannel coupling analysis code for lead-cooled fast reactor
    Wang, Chi
    Cao, Liankai
    Zhang, Xuebei
    Shen, Chong
    Chen, Hongli
    INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2019, 43 (14) : 8447 - 8462
  • [24] Core design investigation for a SUPERSTAR small modular lead-cooled fast reactor demonstrator
    Bortot, S.
    Moisseytsev, A.
    Sienicki, J. J.
    Artioli, Carlo
    NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (08) : 3021 - 3031
  • [25] Core design of long-cycle small modular lead-cooled fast reactor
    Tung Dong Cao Nguyen
    Choe, Jiwon
    Ebiwonjumi, Bamidele
    Lemaire, Matthieu
    Lee, Deokjung
    INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2019, 43 (01) : 254 - 273
  • [26] Preliminary design and analysis on the cogeneration system for Small Modular Lead-cooled Fast Reactor
    Xu, Chi
    Li, Yang
    Jin, Ming
    Kong, Fanli
    Gao, Sheng
    Zhou, Tao
    Bai, Yunqing
    APPLIED THERMAL ENGINEERING, 2020, 174
  • [27] Research on Multi-Physics Coupling Method of Pool Type Fast Reactor Based on CFD
    Zhao P.
    Liu Z.
    Yu T.
    Liu P.
    Xie J.
    Chen Z.
    Hedongli Gongcheng/Nuclear Power Engineering, 2020, 41 (06): : 36 - 44
  • [28] Analysis of Transient Thermal-Hydraulic and Safety of Lead-Cooled Fast Reactor Based on Unified Coupling Framework
    Luo X.
    Zhang X.
    Chen H.
    Wang S.
    Guo C.
    Wang C.
    Hedongli Gongcheng/Nuclear Power Engineering, 2021, 42 : 11 - 16
  • [29] Simulation of a loss of flow transient of a small Lead-Cooled reactor using a CFD-Based model
    Hernandez, Cuauhtemoc Reale
    Wallenius, Janne
    Luxat, John
    NUCLEAR ENGINEERING AND DESIGN, 2023, 412
  • [30] GeN-Foam: a novel OpenFOAM® based multi-physics solver for 2D/3D transient analysis of nuclear reactors
    Fiorina, Carlo
    Clifford, Ivor
    Aufiero, Manuele
    Mikityuk, Konstantin
    NUCLEAR ENGINEERING AND DESIGN, 2015, 294 : 24 - 37