铅冷快堆冷却剂温度控制系统中流量参数稳定性分析
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摘要
冷却剂温度控制系统是铅冷快堆控制系统中的主要子系统之一。在对其研究过程中,系统稳定性分析是最为重要的环节与基础,其结果直接决定控制系统的运行是否安全可靠。本文主要从设计参数的角度出发,分析了恒定热功率下一、二回路冷却剂流量稳态运行值变化对冷却剂温度控制系统稳定性的影响。分析结果表明,在一回路中,提升冷却剂流量的运行稳态值对系统是否稳定不会产生影响,但较大的流量会降低系统的稳定程度,增加系统的运行风险;在二回路中,增大给水流量能明显增加系统的临界开环增益,扩大稳定范围区间,但对于系统稳定程度的影响相对有限。本研究结果将对铅冷快堆参数设计与系统安全运行提供重要参考。
The coolant temperature control system is one of the main subsystems in the control system of lead-cooled fast reactor. In this study,stability analysis is the most important segment and foundation,which directly determines whether the control system operation is safe and reliable. From the perspective of parameter design,the influence of the steadyoperation value from the coolant flow in the primary and secondary loops on the stability of the coolant temperature control system was mainly analyzed when the heating power was maintained in constant. The analysis results show that in the primary circuit,the increase of steady-state value of coolant flow will not affect the stability of the system. However,the larger flow rate will reduce the stability degree and increase the operating risk of the system. In the secondary circuit,increasing the water supply flow can obviously make the critical opening loop gain of the system increased and expand the stability range,but the impact on the system stability is limited. These results will provide an important reference for the parameter design and safety operation of lead-cooled fast reactor.
The coolant temperature control system is one of the main subsystems in the control system of lead-cooled fast reactor. In this study,stability analysis is the most important segment and foundation,which directly determines whether the control system operation is safe and reliable. From the perspective of parameter design,the influence of the steadyoperation value from the coolant flow in the primary and secondary loops on the stability of the coolant temperature control system was mainly analyzed when the heating power was maintained in constant. The analysis results show that in the primary circuit,the increase of steady-state value of coolant flow will not affect the stability of the system. However,the larger flow rate will reduce the stability degree and increase the operating risk of the system. In the secondary circuit,increasing the water supply flow can obviously make the critical opening loop gain of the system increased and expand the stability range,but the impact on the system stability is limited. These results will provide an important reference for the parameter design and safety operation of lead-cooled fast reactor.
引文
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[12]胡寿松.自动控制原理[M].6版.北京:科学出版社,2013:432-436,491-492.
[2]胡大璞,袁红球.新型快堆--铅冷快堆的堆物理特征[J].核动力工程,1995,卷(3):194-198.
[3]JIN Ming,CHEN Zhao,CHEN Hongli,et al.Natural Circulation Characteristics of China Lead Alloy Cooled Research Reactor CLEAR-I[C]//NUTHOS-9.Kaohsiung,Taiwan:[s.n.],2012.
[4]WU Yican.Overview of liquid lithium lead breeder blanket program in China[J].Fusion Engineering and Design,2011,86:2343-2346.
[5]张光雨,宋勇,徐鹏,等.基于RELAP5-HD的中国铅基研究实验堆模拟机热工水力模型开发与分析[J].原子能科学技术,2015,49(b05):153-160.
[6]吴宜灿,王明煌,黄群英,等.铅基反应堆研究现状与发展前景[J].核科学与工程,2015,35(2):213-221.
[7]Allen T R,Crawford D C.Lead-Cooled Fast Reactor Systems and the Fuels and Materials Challenges[J].Science&Technology of Nuclear Installations,2007,2007(3).
[8]LI H,HUANG X,ZHANG L.A lumped parameter dynamic model of the helical coiled once-through steam generator with movable boundaries[J].Nuclear Engineering and Design,2008,238(7):1657-1663.
[9]WU Yican.CLEAR-S:An integrated non-nuclear test facility for china lead-based research reactor[J].International Journal of Energy Research,2016,40:1951-1956.
[10]Knowles J B.2.Adequacy of Linear Models and Nuclear Reactor Dynamics[M]//Nuclear Electric Power:Safety,Operation,and Control Aspects.John Wiley&Sons,Inc.2013:34-55.
[11]李磊,游兆永.关于实矩阵A的稳定度[J].应用数学学报1994,17(3):462-465.
[12]胡寿松.自动控制原理[M].6版.北京:科学出版社,2013:432-436,491-492.