Analysis of Ex-core Source Range Detector Count Rate in PWR Nuclear Power Plant

被引:0
|
作者
Ding Q. [1 ]
Wang M. [1 ]
Li W. [2 ]
Zhou Y. [1 ]
Mei Q. [1 ]
Ye G. [2 ]
机构
[1] Shanghai Nuclear Engineering Research & Design Institute Co. Ltd., Shanghai
[2] CNNC Nuclear Power Operations Management Co. Ltd., Haiyan
来源
| 1600年 / Atomic Energy Press卷 / 54期
关键词
Count rate; Secondary neutron source; Source range detector; Startup without neutron source;
D O I
10.7538/yzk.2019.youxian.0264
中图分类号
TL48 []; TM623 [核电厂(核电站)];
学科分类号
摘要
During the startup of pressurized water reactor (PWR) nuclear power plant, the secondary neutron source provides background count rate for the ex-core source range detectors, avoiding measurement blind zone and assuring the reactor's safety. However, the usage of the secondary neutron source will bring biggish economic and environmental burdens and increase the plant operation risk from the secondary neutron source damage. So, the spontaneous fission neutron from irradiated fuel assembly can be used instead, which is called startup without neutron source. In this paper, the calculation method of detector count rate was studied and verified based on the measured data from the operation plant, and it provides a relatively perfect theoretical and methodological process for the theoretical prediction of the count rate of the source range detector. This method can provide theoretical support and reference for detector count rate analysis in demonstration of startup without neutron source, and optimization analysis of secondary neutron source loadage and disposal. © 2020, Editorial Board of Atomic Energy Science and Technology. All right reserved.
引用
收藏
页码:470 / 474
页数:4
相关论文
共 6 条
  • [1] RG 168 Initial test programs for water: Cooled nuclear power plants, (2007)
  • [2] Liao Z., Kong D., Reactor reloading and start-up without neutron source in Qinshan NPP, Nuclear Power Engineering, 31, 2, pp. 141-144, (2010)
  • [3] Li S., Deng L., Xu H., Et al., Usability analyses of source range detector after secondary neutron source canceled, Atomic Energy Science and Technology, 45, 3, pp. 314-318, (2011)
  • [4] Su G., Bao P., Han S., Calculation and verification of secondary neutron source intensity of nuclear reactor, High Power Laser and Particle Beams, 29, 3, (2017)
  • [5] Zhao J., Li X., Yu H., Et al., Preliminary feasibility analysis of application of secondary neutron source in China Experimental Fast Reactor, Atomic Energy Science and Technology, 51, 5, pp. 811-816, (2017)
  • [6] MCNP: A general Monte Carlo N-particle transport code, Version 5, (2003)