期刊文献+

1GW固态燃料熔盐堆运行瞬态分析 被引量:3

Transient analysis with 1-GW solid fuel molten salt reactor
原文传递
导出
摘要 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: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:This study aims at disturbed transient analysis of TMSR for fundamental comprehension of its safety and operation characteristics. Methods: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: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: 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.
出处 《核技术》 CAS CSCD 北大核心 2016年第10期89-94,共6页 Nuclear Techniques
基金 中国科学院战略性先导科技专项(No.XDA02010000)资助~~
关键词 熔盐堆 运行瞬态 RELAP5 控制棒 RELAP5 Simulink TMSR Transient analysis Simulink Control rod
  • 相关文献

参考文献7

二级参考文献40

  • 1林萌,胡锐,杨燕华.核电厂控制与保护系统动态仿真[J].核动力工程,2004,25(6):562-566. 被引量:10
  • 2LING AO Nuclear Power Company LTD. System Design Manual [R]. LANPC, 1998.
  • 3LING AO Nuclear Power Company LTD. Test Report, PL127RRCR60LSUM45GN (TR 1 RRC 60) [R]. LANPC, 2002.
  • 4The RELAP5Code Development Team.RELAP5/MOD3.3CODE MANUAL VOLUME V[M].USA:In-formation Systems Laboratories,Inc.2001.
  • 5Westinghouse Electric Company LLC.AP1000Design Control Document[Z].Revision10.2004.
  • 6The RELAP5 Code Development Team. RELAP5/MOD3 Code Manual[M]. USA: Idaho National Engineering Laboratory, 1995.
  • 7Postel J. Internet Protocol[M]. RFC 791(Standard), September 1981.
  • 8Postel J. Transmission Control Protocol[M]. RFC 793(Standard), September 1981.
  • 9Geist, A. PVM3 User's Guide and Reference, ORNL:TM-12187 [M]. Oak Ridge National Laboratory, 1994.
  • 10Jeong, J-J. Development of a Multi-Dimensional Thermal-Hydraulic System Code, MARS 1.3.1 [J]. Annals of Nuclear Energy, 1999, 26:1611~1642.

共引文献45

同被引文献12

引证文献3

二级引证文献5

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部