Development of TREND dynamics code for molten salt reactors

Wen Yu; Jian Ruan; Long He; James Kendrick; Yang Zou; Hongjie Xu

doi:https://doi.org/10.1016/j.net.2020.07.030

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자료유형: 학술저널

저자정보: Wen Yu (Shanghai Institute of Applied Physics Chinese Academy of Sciences) Jian Ruan (Shanghai Institute of Applied Physics Chinese Academy of Sciences) Long He (Shanghai Institute of Applied Physics Chinese Academy of Sciences) James Kendrick (University of California) Yang Zou (Shanghai Institute of Applied Physics Chinese Academy of Sciences) Hongjie Xu (Shanghai Institute of Applied Physics Chinese Academy of Sciences)

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제53권 제2호

발행연도: 2021.2

수록면: 455 - 465 (11page)

DOI: https://doi.org/10.1016/j.net.2020.07.030

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The Molten Salt Reactor (MSR), one of the six advanced reactor types of the 4th generation nuclearenergy systems, has many impressive features including economic advantages, inherent safety andnuclear non-proliferation. This paper introduces a system analysis code named TREND, which isdeveloped and used for the steady and transient simulation of MSRs. The TREND code calculates thedistributions of pressure, velocity and temperature of single-phase flows by solving the conservationequations of mass, momentum and energy, along with a fluid state equation. Heat structures coupledwith the fluid dynamics model is sufficient to meet the demands of modeling MSR system-level thermalhydraulics. The core power is based on the point reactor neutron kinetics model calculated by the typicalRunge-Kutta method. An incremental PID controller is inserted to adjust the operation behaviors. Theverification and validation of the TREND code have been carried out in two aspects: detailed code-tocodecomparison with established thermal-hydraulic system codes such as RELAP5, and validationwith the experimental data from MSRE and the CIET facility (the University of California, Berkeley’sCompact Integral Effects Test facility).The results indicate that TREND can be used in analyzing thetransient behaviors of MSRs and will be improved by validating with more experimental results with thesupport of SINAP

#Molten salt reactor #Transient analysis #Code development #Verification and validation

참고문헌 (27)

참고문헌 신청

M. W. Rosenthal / 1970 / Molten-salt reactorsdpistory, states, and potential / Nucl. App. Technol 8:107~117

C. Forsberg / 2005 / The advanced high-temperature reactor: high-temperature fuel, liquid salt coolant, liquid-metal-reactor plant / Prog. Nucl. Energy 47:32~43

J. Serp / 2014 / The molten salt reactor(MSR)in generation IV : overview and perspectives / Prog. Nucl. Energy 77:308~319

M. H. Jiang / 2012 / Advanced fission energy program-TMSR nuclear energy system / Bull. Chin. Acad. Sci 3:366~374

J. Krepel / 2005 / DYN1D-MSR dynamics code for molten salt reactors / Ann. Nucl. Energy 32:1799~1824

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