Characteristic Analysis of Feed Water System in Multi-module Once-through Steam Generator

被引:0
|
作者
Bi D. [1 ]
Duan T. [1 ]
Jia Y. [1 ]
Liu Y. [1 ]
Zhang H. [2 ]
机构
[1] Division of Reactor Engineering Technology Research, China Institute of Atomic Energy, Beijing
[2] North Regional Office of Nuclear and Radiation Safety Inspection, National Nuclear Safety Administration, Beijing
关键词
Dynamic characteristic; Multi-module; Once-through steam generator; Sodium-cooled fast reactor; Static characteristic;
D O I
10.7538/yzk.2018.youxian.0854
中图分类号
学科分类号
摘要
To provide references for the design of feed water control system and the once-through steam generators, the simulation models of feed water system of Chinese demonstration fast reactor were built, and both the static and dynamic characteristics of this system were analyzed. The influence of sodium temperature at evaporator outlet and the flow deviation in primary side of each model on the work state of each model was analyzed, and the limits of these parameters were figured out. The results show that sodium temperature at evaporator outlet and the flow deviation in primary side of each model must be limited to keep each model working stably. © 2019, Editorial Board of Atomic Energy Science and Technology. All right reserved.
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收藏
页码:2198 / 2203
页数:5
相关论文
共 12 条
  • [1] Demore L.A., Bapna B.H., Matta J.V., The plant control system design for the Clinch River Breeder Reactor Plant, Proceedings of the 3rd Power Plant Dynamics, Control and Testing Symposium, (1977)
  • [2] Tang Y.S., Coffield R.D., Merkley R.A., Thermal Analysis of liquid Metal Fast Breeder Reactors, (1978)
  • [3] Chapelot M., Instrumentation, control and monitoring systems, Nuclear Engineering International, 16, 182, pp. 577-580, (1971)
  • [4] Xu M., Development of fast breeder reactor and experiment fast reactor in China, Nuclear Power Engineering, 21, 1, pp. 34-38, (2000)
  • [5] Sadler I.A., Atthey D.R., Scruton B., The complete simulation of dynamic instability in a sodium-heated steam generation, Dynamics and Control in Nuclear Power Stations, pp. 173-180, (1992)
  • [6] Donaldson A.J., Once-through steam generator heat transfer models for SIR, Dynamics and Control in Nuclear Power Stations, pp. 125-132, (1992)
  • [7] Bruens N.W.S., Brukx J.F.L.M., Latzko D.G.H., Et al., Modeling of nuclear steam generator dynamics, Proceedings of the Second Power Plant Dynamics, Control and Testing Symposium, (1975)
  • [8] Xie H., Zhang J., Jia D., Et al., Thermal hydraulic predictions of once-through steam generator, Chinese Journal of Nuclear Science and Engineering, 17, 2, pp. 97-102, (1997)
  • [9] Zhang W., Bian X., Xia G., Simulation research of static and dynamic characteristic of once-though steam generator in concentric annulus tube, Proceedings of CSEE, 27, 5, pp. 76-80, (2007)
  • [10] RELAP5/MOD3.3 code manual Volume Ⅰ: Code structure, system models, and solution methods, (2001)