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1.中国科学院上海应用物理研究所 嘉定园区 上海 201800
2.中国科学院大学 北京 100049
Received:30 November 2017,
Revised:19 January 2018,
Published:10 June 2018
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Maosong CHENG, Ming LIN, Xiandi ZUO, et al. Development and validation of a three-dimensional hexagonal nodal time-spatial kinetics code based on exponential transform[J]. Nuclear techniques, 2018, 41(6): 060604
Maosong CHENG, Ming LIN, Xiandi ZUO, et al. Development and validation of a three-dimensional hexagonal nodal time-spatial kinetics code based on exponential transform[J]. Nuclear techniques, 2018, 41(6): 060604 DOI: 10.11889/j.0253-3219.2018.hjs.41.060604.
熔盐堆是第四代先进反应堆6个候选堆型之一,包括液态燃料熔盐堆和固态燃料熔盐堆,其中固态燃料熔盐堆采用高温熔盐作为冷却剂,具备高温、常压、高功率密度等优点,在固有安全性以及经济性上具有极大的优势和潜力。为了开展六角形燃料组件熔盐冷却先进高温堆瞬态分析和安全评估,基于指数变换和六角形节块展开法,开发了三维时空动力学程序TCORE3D-HEX。选取了两个俄罗斯VVER型压水堆国际基准题算例,通过对比及分析国际上几种适用于六角形几何的时空动力学程序,验证TCORE3D-HEX程序的正确性。结果表明:基于指数变换和六角形节块法开发的三维时空动力学程序数值计算结果与国际上其他程序计算结果符合得很好,初步验证了程序的正确性,为钍基熔盐堆核能系统(Thorium Molten Salt Reactor,TMSR)设计提供了可靠的分析和评估工具。
Background
2
Molten salt reactor is one of the six Generation Ⅳ advanced reactor concepts selected by Generation Ⅳ International Forum (GIF)
which can be divided into liquid-fueled and solid-fueled molten salt reactor. The solid-fueled molten salt reactor uses high-temperature liquid-salt as coolant and is provided with features of high-temperature
low-pressure and high-power density
as well as great advantage and potential in inherent safety.
Purpose
2
This study aims to develop and validate a three-dimensional time-spatial kinetics code named TCORE3D-HEX which can be used to carry out transient analysis and safety assessment of molten salt-cooled reactor with hexagonal fuel assembly.
Methods
2
The exponential transform and hexagonal nodal expand methods are applied in the TCORE3D-HEX kinetics code. Two VVER (Vodo-Vodyanoi Energetichesky Reaktor) international benchmarks are selected to validate the validity of the TCORE3D-HEX code by comparing with several three-dimensional hexagonal nodal time-spatial kinetics codes.
Results
2
The results indicate that the numerical result of the TCORE3D-HEX code are in good agreement with that of other kinetics codes.
Conclusion
2
The developed kinetics code is validated on VVER pressurized water reactor (PWR)
and will be a reliable analytical and assessment tool for the design of innovative molten salt-cooled reactor in thorium molten salt reactor (TMSR).
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