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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
[ "张洁, 男, 1982年出生, 2010年于中国科学院近代物理研究所获硕士学位, 现为博士研究生, 研究方向为反应堆热工水力", "ZHANG Jie, male, born in 1982, graduated from Institute of Modern Physics, Chinese Academy of Sciences with a master's degree in 2010, doctoral student, focusing on thermal hydraulic calculation of reactor" ]
收稿日期:2016-06-15,
修回日期:2016-06-29,
纸质出版日期:2016-10
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张洁, 李明海, 何龙, 等. 1 GW固态燃料熔盐堆运行瞬态分析[J]. 核技术, 2016,39(10):100605
Jie ZHANG, Minghai LI, Long HE, et al. Transient analysis with 1-GW solid fuel molten salt reactor[J]. Nuclear techniques, 2016, 39(10): 100605
张洁, 李明海, 何龙, 等. 1 GW固态燃料熔盐堆运行瞬态分析[J]. 核技术, 2016,39(10):100605 DOI: 10.11889/j.0253-3219.2016.hjs.39.100605.
Jie ZHANG, Minghai LI, Long HE, et al. Transient analysis with 1-GW solid fuel molten salt reactor[J]. Nuclear techniques, 2016, 39(10): 100605 DOI: 10.11889/j.0253-3219.2016.hjs.39.100605.
钍基熔盐堆(Thorium-based Molten Salt Reactor,TMSR)作为一种新的堆型,具有独特的安全与运行特性。研究其热工水力特性,对其进行瞬态分析,将有助于深刻理解该反应堆。本文介绍了1 GW固态熔盐堆的堆芯设计方案,并描述了用于瞬态分析的详细程序结构。其中,利用RELAP5对其热工水力模型进行模拟;利用Simulink对其控制系统模型进行模拟。通过预期运行瞬态,例如功率降低、堆芯反应性引入、二回路温度变化等工况显示了其运行特性,并验证了控制系统可以使反应堆达到安全稳定状态,而不触发保护系统动作。
Background
2
As a new type of reactor
thorium-based molten salt reactor (TMSR) has unique safety and operation characteristics. Its thermal-hydraulic features are enormously different from other reactors
thus worth doing transient analysis.
Purpose
2
This study aims at disturbed transient analysis of TMSR for fundamental comprehension of its safety and operation characteristics.
Methods
2
The structure and design scheme of the core of 1-GW solid fuel thorium-based molten salt reactor (TMSR-SF) have been presented. Structural emulation platform for transient analysis is proposed with the thermo-hydraulic model being developed on the basis of RELAP5
and the control system model being constructed by using the MATLAB/Simulink software.
Results
2
The results of emulation test for operational transient
such as rapid power reduction
step load reducing
linear load reducing and temperature of secondary loop inlet reducing show that the reactor control system is effective to bring the reactor into a safe and steady state without actuation of reactor protection system.
Conclusion
2
Analysis results show that the design satisfied the requirements of 1-GW TMSR-SF operational transient. It also indicates that the platform can perfectly simulate the variable power transient conditions.
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戴叶. 1000 MW固体燃料规则球床熔盐堆初步物理设计报告[R].上海:中国科学院上海应用物理研究所, 2013
DAI Ye. 1000 MW ordered bed fluoride-salt-cooled high-temperature reactor concept[R]. Shanghai:Shanghai Institute of Applied Physics, Chinese Academy of Sciences, 2013
龚 湛 , 林 萌 , 刘 鹏飞 , . AP1000核电站仿真分析平台的研发 . 热力发电 , 2012 . 41 ( 3 ): 32 - 36 . http://www.cnki.com.cn/Article/CJFDTOTAL-RLFD201203010.htm .
Zhan GONG , Meng LIN , Pengfei LIU , . Development of emulation analysis platform for AP1000 nuclear power plant . Thermal Power Generation , 2012 . 41 ( 3 ): 32 - 36 . http://www.cnki.com.cn/Article/CJFDTOTAL-RLFD201203010.htm .
刘 立欣 , 郑 利民 , 周 全福 . AP1000核电厂典型的运行瞬态分析 . 核技术 , 2012 . 35 ( 11 ): 869 - 876 . http://www.cnki.com.cn/Article/CJFDTOTAL-HJSU201211015.htm .
Lixin LIU , Limin ZHENG , Quanfu ZHOU . Preliminary study on operational transient analysis for AP1000 . Nuclear Techniques , 2012 . 35 ( 11 ): 869 - 876 . http://www.cnki.com.cn/Article/CJFDTOTAL-HJSU201211015.htm .
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