Research on Multi-Physics Coupling Method of Pool Type Fast Reactor Based on CFD

被引：0

作者：

Zhao P. ^{[1
,2
,3
]}

Liu Z. ^{[1
]}

Yu T. ^{[1
]}

Liu P. ^{[1
]}

Xie J. ^{[1
]}

Chen Z. ^{[1
]}

机构：

[1] School of Nuclear Science and Technology, University of South China, Hengyang

[2] Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu

[3] Cooperative Innovation Center for Nuclear Fuel Cycle Technology and Equipment, University of South China, Hengyang

来源：

Hedongli Gongcheng/Nuclear Power Engineering | 2020年 / 41卷 / 06期

关键词：

Computational fluid dynamics(CFD); Fuel pin heat transfer model; Multi-physical coupling; Point kinetics model; Pool-type fast reactor;

D O I：

10.13832/j.jnpe.2020.06.0036

中图分类号：

学科分类号：

摘要：

Based on the critical/subcritical point kinetics model, the fuel pin heat transfer model, and the auxiliary thermal hydraulic models such as the heat exchanger model and the porous media model, a multi-physical coupling code CFD/PF was developed by means of the explicit iteration method, dynamic link library technique (DLL) and user-defined functions (UDF) of FLUENT. The CFD/PF was used to carry out the simulation of SNCLFR-100 unprotected transient of over power (UTOP) of a small natural circulation LBE cooled fast reactor, and the code-to-code comparison analysis was conducted with the renowned multi-physical coupling code SIMMER-III. The results indicated that the CFD/PF simulation results are in a good agreement with SIMMER-III calculation results, and the multi-physical analysis method and code development have been achieved initial success, which can be used to analyze the complex three-dimensional flow and heat transfer phenomena in pool-type fast reactors. © 2020, Editorial Board of Journal of Nuclear Power Engineering. All right reserved.

引用

页码：36 / 44

页数：8

共 12 条

[1] ZHANG Y, WANG C, LAN Z, Et al., Review of thermal-hydraulic issues and studies of lead-based fast reactors, Renewable and Sustainable Energy Reviews, 120, (2020)
[2] TENCHINE D., Some thermal hydraulic challenges in sodium cooled fast reactors, Nuclear Engineering and Design, 240, 5, pp. 1195-1217, (2010)
[3] MYLONAKIS A G, VARVAYANNI M, CATSAROS N, Et al., Multi-physics and multi-scale methods used in nuclear reactor analysis, Annals of Nuclear Energy, 72, pp. 104-119, (2014)
[4] TOBITA Y, KONDO S, YAMANO H, Et al., The development of SIMMER-III, an advanced computer program for LMFR safety analysis, and its application to sodium experiments, Nuclear Technology, 153, 3, pp. 245-255, (2006)
[5] CHEN X N, LI R, BELLONI F, Et al., Safety studies for the MYRRHA critical core with the SIMMER-III code, Annals of Nuclear Energy, 110, pp. 1030-1042, (2017)
[6] FIORINA C, KERKAR N, MIKITYUK K, Et al., Development and verification of the neutron diffusion solver for the GeN-Foam multi-physics platform, Annals of Nuclear Energy, 96, pp. 212-222, (2016)
[7] YANG W S., Fast reactor physics and computational methods, Nuclear Engineering and Technology, 44, 2, pp. 177-198, (2012)
[8] BANDINI G, MELONI P, POLIDORI M., Thermal-hydraulics analyses of ELSY lead fast reactor with open square core option, Nuclear Engineering and Design, 241, 4, pp. 1165-1171, (2011)
[9] GRASSO G, PETROVICH C, MATTIOLI D, Et al., The core design of ALFRED, a demonstrator for the European lead-cooled reactors, Nuclear Engineering and Design, 278, pp. 287-301, (2014)
[10] SCHIKORR W M., Assessments of the kinetic and dynamic transient behavior of sub-critical systems (ADS) in comparison to critical reactor systems, Nuclear engineering and design, 210, 1-3, pp. 95-123, (2001)

← 1 2 →