Scholarlink

In a CPR1000 nuclear power plant, during stable automatic control operation, the average temperature control system showed frequent control rod (R-rod) movements, with a maximum of more than 300 times a day on average. The frequent R-rod movements increase the wear of the control rod mechanism as well as the risk of dropping or slipping, which affects the safe and stable operation of the unit to a certain extent. Thus, this paper analyzes the root cause of the R rod disturbance phenomenon in a CPR1000 unit and formulates various solutions. Based on the field measurement data, this paper extracts the relevant input, output and intermediate link data of the average temperature control system, combines with the numerical simulation analysis of the upper chamber, and analyzes the root causes of the R-rod perturbation in various aspects. From the perspective of different causes, corresponding solutions are given, and the reasonableness of the solutions is demonstrated through control system simulation. The results show that the main factors affecting the R-rod perturbation are the temperature fluctuation in the hot leg and cold leg. The root cause is the large dispersion of the radial power distribution of the core and the insufficient intermixing of the fluids when they flow through the upper chamber. The solution is, on the one hand, to reduce the temperature fluctuation, the loading plan can be optimized to reduce the core power distribution dispersion, and on the other hand, from the perspective of the average temperature control, under the premise of guaranteeing nuclear safety, the control parameters can be optimized to reduce the action of the R rod. In the actual operation of power plants, the two aspects are usually considered in combination to ensure safety while improving fuel economy. The operating effect of the power plant shows that the parameter optimization combined with the optimization of the loading plan can effectively alleviate the phenomenon of R rod perturbation. This solution is of great significance for the design and operation of new reactor types such as Hualong reactor.

错误：搜索内容不能为空，请输入英文关键词
错误：关键词超出字数限制，请精简
高级检索

Analysis of the Cause of R ROD Perturbation and Solution Research Based on CPR1000 Nuclear Power Plant

  • 会议论文

  • 发表日期：

    2026年

查看全文
  • Desheng Jin,
  • Wei Zhang,
  • Yating Tian,
  • Tianming Ruan,
  • Xiong Zheng

摘要

In a CPR1000 nuclear power plant, during stable automatic control operation, the average temperature control system showed frequent control rod (R-rod) movements, with a maximum of more than 300 times a day on average. The frequent R-rod movements increase the wear of the control rod mechanism as well as the risk of dropping or slipping, which affects the safe and stable operation of the unit to a certain extent. Thus, this paper analyzes the root cause of the R rod disturbance phenomenon in a CPR1000 unit and formulates various solutions. Based on the field measurement data, this paper extracts the relevant input, output and intermediate link data of the average temperature control system, combines with the numerical simulation analysis of the upper chamber, and analyzes the root causes of the R-rod perturbation in various aspects. From the perspective of different causes, corresponding solutions are given, and the reasonableness of the solutions is demonstrated through control system simulation. The results show that the main factors affecting the R-rod perturbation are the temperature fluctuation in the hot leg and cold leg. The root cause is the large dispersion of the radial power distribution of the core and the insufficient intermixing of the fluids when they flow through the upper chamber. The solution is, on the one hand, to reduce the temperature fluctuation, the loading plan can be optimized to reduce the core power distribution dispersion, and on the other hand, from the perspective of the average temperature control, under the premise of guaranteeing nuclear safety, the control parameters can be optimized to reduce the action of the R rod. In the actual operation of power plants, the two aspects are usually considered in combination to ensure safety while improving fuel economy. The operating effect of the power plant shows that the parameter optimization combined with the optimization of the loading plan can effectively alleviate the phenomenon of R rod perturbation. This solution is of great significance for the design and operation of new reactor types such as Hualong reactor.