Research on Optimum State of Sodium-cooled Fast Reactor with Loss of Steam Generator Module

被引:0
|
作者
Wang L.-X. [1 ]
Yang H.-Y. [1 ]
Yang X.-Y. [1 ]
Liu Y.-Z. [1 ]
Wang X.-K. [1 ]
Qi S.-P. [1 ]
Ye S.-S. [1 ]
机构
[1] China Institute of Atomic Energy, P. O. Box 275-34, Beijing
来源
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2017年 / 51卷 / 02期
关键词
Loss of module; Modular steam generator; Optimum state; Sodium-cooled fast reactor;
D O I
10.7538/yzk.2017.51.02.0292
中图分类号
学科分类号
摘要
By adopting the design proposal of modular steam generator, the load factor of the sodium-cooled fast reactor (SFR) could be improved. The state of the plant would be about to change in case of loss of steam generator modules in the daily operation, and the modulatory state of the plant should be given by means of design and research. This research selected a typical pool-type SFR to study the state of the plant with loss of one of its steam generator modules, which included establishment of a model to the main heat transfer system, massive matching calculation on its main thermal parameters, discard of those projects that did not meet the relevant operating limits, analysis of key parameters and determination of the optimum state. This work lays a foundation for the design of the state of SFR with loss of steam generator modules. © 2017, Editorial Board of Atomic Energy Science and Technology. All right reserved.
引用
收藏
页码:292 / 298
页数:6
相关论文
共 7 条
  • [1] Cochran T.B., Feiveson H.A., Patterson W., Et al., Fast breeder reactor programs: History and status, (2010)
  • [2] Nandakumar R., Athmalingam S., Balasubramaniyan V., Et al., Steam generators for future fast breeder reactors, Energy Procedia, 7, pp. 351-358, (2011)
  • [3] Chetal S.C., Past steam generator operating experiences and lessons learnt, (1995)
  • [4] Chetal S.C., Bhoje S.B., Kale R.D., Et al., Conceptual design of heat transport systems and components of PFBR-NSSS, (1995)
  • [5] Athmalingam S., Steam generator for PFBR and future FBR, (2011)
  • [6] Athmalingam S., Intermediate heat exchanger for PFBR and future FBR, (2011)
  • [7] Zhang J., Li J., Sang W.-L., Modular modeling and transient simulation research of once-though steam generator for sodium-cooled fast reactor, Nuclear Power Engineering, 20, 1, pp. 79-83, (1999)