Simulation of a molten salt fast reactor using the COMSOL multiphysics software

D. H. Daher; M. Kotb; A. M. Khalaf; Moustafa S. El-Koliel; Abdelfattah Y. Soliman

doi:10.1007/s41365-020-00833-3

Your Location：

Home >

Browse articles >

Simulation of a molten salt fast reactor using the COMSOL multiphysics software

NUCLEAR ENERGY SCIENCE AND ENGINEERING | Updated：2021-01-26

- Simulation of a molten salt fast reactor using the COMSOL multiphysics software
- Simulation of a molten salt fast reactor using the COMSOL multiphysics software
- 核技术（英文版） 2020年31卷第12期文章编号：115
- Affiliations：
  
  1.Department of Physics, Faculty of Science, Al-Azhar University, Cairo, Egypt
  2.Department of Reactors, Nuclear Research Center, Atomic Energy Authority, Cairo, Egypt
  3.Nuclear Engineering Department, King Abdulaziz University, Saudi Arabia
- Author bio：
  
  Corresponding author, mahmoudkotb@azhar.edu.eg
- Funds：
- DOI：10.1007/s41365-020-00833-3
  中图分类号：
Scan for full text
D. H. Daher, M. Kotb, A. M. Khalaf, 等. Simulation of a molten salt fast reactor using the COMSOL multiphysics software[J]. 核技术（英文版）, 2020,31(12):115

D. H. Daher, M. Kotb, A. M. Khalaf, et al. Simulation of a molten salt fast reactor using the COMSOL multiphysics software[J]. Nuclear Science and Techniques, 2020,31(12):115
D. H. Daher, M. Kotb, A. M. Khalaf, 等. Simulation of a molten salt fast reactor using the COMSOL multiphysics software[J]. 核技术（英文版）, 2020,31(12):115 DOI： 10.1007/s41365-020-00833-3.

D. H. Daher, M. Kotb, A. M. Khalaf, et al. Simulation of a molten salt fast reactor using the COMSOL multiphysics software[J]. Nuclear Science and Techniques, 2020,31(12):115 DOI： 10.1007/s41365-020-00833-3.

摘要

Abstract

In this study, COMSOL v5.2 Multiphysics software was utilized to perform coupled neutronics and thermal-hydraulics simulations of a molten salt fast reactor, and the SCALE v6.1 code package was utilized to generate the homogenized cross-section data library. The library’s 238 cross-section groups were categorized into nine groups for the simulations in this study. The results of the COMSOL model under no fuel flow conditions were verified using the SCALE v6.1 code results, and the results of the neutronics and thermal-hydraulics simulations were compared to the results of previously published studies. The results indicated that the COMSOL model that includes the cross-section library generated by the SCALE v6.1 code package is suitable for the steady-state analysis and design assessment of molten salt fast reactors. Subsequently, this model was utilized to investigate the neutronics and thermal-hydraulics behaviors of the reactor. Multiple designs were simulated and analyzed in this model, and the results indicated that even if the wall of the core is curved, hotspots occur in the upper and lower portions of the core’s center near the reflectors. A new design was proposed that utilizes a flow rate distribution system, and the simulation results of this design showed that the maximum temperature in the core was approximately 1032 K and no hotspots occurred.

关键词

Keywords

references

D. Buckthorp. Introduction to Generation IV nuclear reactors. Structural Materials for Generation IV Nuclear Reactors. Elsevier, 2017. p. 1-22. https://doi.org/10.1016/B978-0-08-100906-2.00001-Xhttps://doi.org/10.1016/B978-0-08-100906-2.00001-X.

R. Li, S. Wang, A. Rineiski, et al. Transient analyses for a molten salt fast reactor with optimized core geometry. Nucl. Eng. Design 292:164-176 (2015). https://doi.org/10.1016/j.nucengdes.2015.06.011https://doi.org/10.1016/j.nucengdes.2015.06.011

M. Brovchenko, J.-L. Kloosterman, L. Luzzi, et al. Neutronic benchmark of the molten salt fast reactor in the frame of the EVOL and MARS collaborative projects. EPJ Nucl. Sci. Technol. 5:2 (2019). https://doi.org/10.1051/epjn/2018052https://doi.org/10.1051/epjn/2018052

E. Merle-Lucotte, M. Allibert, M. Brovchenko, et al. Introduction to the Physics of Thorium Molten Salt Fast Reactor (MSFR) Concepts. Thorium Energy for the World, Cham: Springer International Publishing; 2016. p. 223-231. https://doi.org/10.1007/978-3-319-26542-1_34https://doi.org/10.1007/978-3-319-26542-1_34

M. Aufiero, A. Cammi, O. Geoffroy, et al. Development of an OpenFOAM model for the Molten Salt Fast Reactor transient analysis. Chem.Engineering Sci. 111:390-401 (2014). https://doi.org/10.1016/j.ces.2014.03.003https://doi.org/10.1016/j.ces.2014.03.003

C. Fiorina, D. Lathouwers, M. Aufiero, et al. Modelling and analysis of the MSFR transient behaviour. Ann. Nucl. Energy 64: 485-498 (2014). https://doi.org/10.1016/j.anucene.2013.08.003https://doi.org/10.1016/j.anucene.2013.08.003

T. Hu, L. Cao, H. Wu, et al. Coupled neutronics and thermal-hydraulics simulation of molten salt reactors based on OpenMC/TANSY. Ann. Nucl. Energy 109:260-276 (2017). https://doi.org/10.1016/j.anucene.2017.05.002https://doi.org/10.1016/j.anucene.2017.05.002

A. Laureau, M. Aufiero, P.R. Rubiolo, et al. Coupled neutronics and thermal-hydraulics transient calculations based on a fission matrix approach: Application to the Molten Salt Fast Reactor. 2015.

A. Laureau, P.R. Rubiolo, D. Heuer, et al. Coupled neutronics and thermal-hydraulics numerical simulations of a Molten Fast Salt Reactor (MFSR). Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo 2014. https://doi.org/10.1051/snamc/201402307https://doi.org/10.1051/snamc/201402307

D. Chandler, J. Freels, G. Maldonado, et al. COMSOL-based Nuclear Reactor Kinetics Studies at the HFIR. 2011.

B.R. Betzler, Powers JJ, Worrall A. Molten salt reactor neutronics and fuel cycle modeling and simulation with SCALE. Ann. Nucl. Energy 101:489-503 (2017). https://doi.org/10.1016/j.anucene.2016.11.040https://doi.org/10.1016/j.anucene.2016.11.040

S.M. Bowman. SCALE 6: Comprehensive Nuclear Safety Analysis Code System. Nucl. Technol. 174:126-148 (2011). https://doi.org/10.13182/NT10-163https://doi.org/10.13182/NT10-163

M. Brovchenko, E. Merle. Optimization of the pre-conceptual design of the MSFR - EVOL project. 2013;2.

M.A. Schultz. Dynamics of Nuclear Reactors.Nucl. Technol.12:415 (1971). https://doi.org/10.13182/NT71-A30993https://doi.org/10.13182/NT71-A30993

COMSOL. Introduction to COMSOL Multiphysics 5.3. 2014;

E.L. Paul, V.A. Atiemo-Obeng, S.M. Krest. Handbook of Industrial Mixing: Science and Practice - Wiley Online Library. John Wiley Sons. 2004.

S. Mulligan. Experimental and numerical analysis of three-dimensional free-surface turbulent vortex flows with strong circulation. 2015.

US Department of Energy. DOE FUNDAMENTALS HANDBOOK NUCLEAR PHYSICS 2, 1993. https://doi.org/DOE-HDBK-1019/2-93https://doi.org/DOE-HDBK-1019/2-93

浏览量

Downloads

CSCD

文章被引用时，请邮件提醒。

Submit

工具集

关联资源

暂无数据