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副教授 硕士生导师

招生学科专业:
核科学与技术 -- 【招收硕士研究生】 -- 材料科学与技术学院
能源动力 -- 【招收硕士研究生】 -- 材料科学与技术学院

性别:男

毕业院校:西安交通大学、University of Michigan

学历:西安交通大学

学位:工学博士学位

所在单位:材料科学与技术学院

办公地点:11307

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Extended development of a Monte Carlo code OpenMC for fuel cycle simulation of molten salt reactor

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所属单位:材料科学与技术学院

发表刊物:Prog. Nucl. Energy

摘要:Adopting liquid fuel and on-line reprocessing scenario are the unique features of molten salt reactor (MSR). Considering lattice code for thermal reactor is not suitable for MSR calculation, batch-wise fuel salt reprocessing scheme and "two-step" deterministic calculations cause some approximations in simulation of MSR on-line continuous fuel reprocessing, this study focuses on the development of a direct calculation method for MSR fuel cycle simulation based on an open source Monte Carlo code OpenMC. A fictitious decay constant and an external source term were introduced into traditional burnup equation for accurate simulation of on-line fuel reprocessing. Finally, a MSR fuel cycle simulation code OpenMCB-MSR was developed by coupling OpenMC and burnup code with Python script. Two pressurized water reactor (PWR) pin cell benchmarks without considering fuel on-line reprocessing, and one actual MSFR fuel cycle benchmark considering fuel on-line reprocessing were used for verification of OpenMCB-MSR. By comparison with reference results, the maximum differences of kinf calculated by OpenMCB-MSR are no more than 400 pcm both for two PWR pin cell benchmarks. Moreover, apart from isotopes with small absolute nuclide number density, all the other isotopes' nuclide number densities show a difference of less than 10%. For MSFR benchmark, the reactivity coefficients, isotope mass evolutions during fuel cycle process, mass evolution of fission products in core and breeding ratio calculated by OpenMCB-MSR show a good agreement with reference results. At equilibrium state, apart from isotopes with very small absolute mass, the differences of other isotopes' mass are no more than 5.0% in comparison with reference results. Benchmark verification results indicate that the method of MSR fuel cycle simulation based on OpenMC code is correct, and OpenMCB-MSR has capability of MSR fuel cycle analysis. © 2019 Elsevier Ltd

备注:v 118,

ISSN号:0149-1970

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发表时间:2020-01-01

合写作者:et al,Qian Zhang,Ting Li