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超临界水冷快堆给水控制系统改进研究

Improvement of Feedwater Control System of Supercritical Water Cooled Fast Reactor
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摘要 超临界水冷快堆是一次直接循环系统。所有的冷却剂在冷却剂泵的驱动下在堆芯被加热后进入汽轮机做功。主蒸汽温度对功率与流量的比值非常敏感。为了抑制主蒸汽的温度变化,本研究中通过增加反馈模块以改进主给水的控制系统。本文采用了三种改进方案,第一种方案中保持功率与给水流量的比值不变,第二种堆芯功率必须随设定值变化,第三种中给水流量随着功率的增加而增加,然后通过计算分析确定控制参数,最后通过功率变化时的运行工况下的对比分析,确定较优的改进方案。 The supercritical water cooled fast reactor(super fast reactor)adopts oncethrough direct cycle.The whole coolant from the feedwater pump is driven to the turbine.The main steam temperature sensitively changes with the power-to-flow ratio.In this study,the feedwater control system of the super fast reactor is improved for suppressing the variation of the main steam temperature through the different feedback terms.Three improvement projects are studied.In the first,it is to keep the ratio of power to feedwater flow rate constant;in the second,the core power must vary to the setpoint in operation,and in the third,the feedwater flow rate increases with increase of core power.Then,the control parameters are optimized by test calculations.At last,the best improvement project is identified by the comparison in power variation operation.
出处 《核科学与工程》 CSCD 北大核心 2014年第4期444-447,461,共5页 Nuclear Science and Engineering
关键词 超临界水冷快堆 给水控制系统 改进 supercritical water cooled fast reactor feedwater control system improvement
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  • 1Y. Oka, S. Koshizuka. Design concept of once-through cycle supercritical-pressure light water cooled reactors [C]. Proc. 1st Int. Syrup. on Supercritical Water-cooled Reactors, Design and Teehnology, Tokyo, Japan, Nov. 6-9, 2000.
  • 2李满昌,王明利.超临界水冷堆开发现状与前景展望[J].核动力工程,2006,27(2):1-4. 被引量:19
  • 3K. Dobashi, Y. Oka, S. Koshizuka. Conceptual design of a high temperature power reactor cooled and moderated by supercritical light water[J]. Ann. Nucl. Energy, 1998, 25: 487-505.
  • 4Y. OKA, Y. Ishiwatari, J. LIU, T. TERAI, and S. NAGASAKI et al. Research Program of a Super Fast Reactor [C]. Proceedings of ICAPP'06, Reno, NV USA, June 4-8, 2006, Paper 6353.
  • 5彭常宏,杨珏.超临界水冷快堆控制系统的设计[J].核电,2010,2:38-41.
  • 6Y. Ishiwatari, Y. Oka and S. Koshizuka. Control of a high temperature supercritical pressure light water cooled and moderated reactor with water rods[J]. J. Nucl. Sci. Technol. , 2003, 40[5]: 298-306.
  • 7Y. Ishiwatari, Y. Oka, S. Koshizuka. Safety of Super LWR (I) : Safety system design [J]. J. Nuel. Sci. Teehnol. , 2005, 42[-11]: 927-934.

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