Reliability Optimization of the Filling and Discharging System for Lead-Based Fast Reactor

被引:0
|
作者
Sun, Yuanli [1 ,2 ]
Chu, Xi [2 ]
Sun, Ming [3 ]
Ge, Daochuan [3 ]
机构
[1] Tsinghua Univ, Inst Nucl & New Energy Technol, Beijing, Peoples R China
[2] Naval Res Inst, Beijing, Peoples R China
[3] Chinese Acad Sci, Inst Nucl Energy Safety Technol, Hefei, Anhui, Peoples R China
基金
中国国家自然科学基金;
关键词
lead-based fast reactor; filling and discharging system; reliability analysis; design optimization; PROBABILISTIC SAFETY ASSESSMENT; CONCEPTUAL DESIGN; STRATEGY; BLANKET;
D O I
10.1109/SRSE56746.2022.10067358
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The lead-based fast reactor is one of the most promising advanced Gen-IV (generation IV) type nuclear power reactors. The filling and discharging system in the primary circuit of the lead-based fast reactor, which is an important system for ensuring the safety of reactor operation, is designed to adjust the coolant level in the reactor vessel. The system is filled with liquid metal, which contains radioactive materials, and it requires high level of safety and reliability. This study performed preliminary reliability analysis for the filling and discharging system of the lead-based fast reactor by using Fault Tree Analysis method. Minimal Cut Sets and failure probability of the filling and discharging system were obtained by using Reliability and Probabilistic Safety Assessment program RiskA, which was developed by Institute of Nuclear Energy Safety Technology, HFIPS, Chinese Academy of Sciences. Some other quantitative analysis results were also obtained, including importance and sensitivity analysis. The reliability analysis results indicated two flaws of the original system design, one is the low reliability, and the other is the lack of redundancy. According to calculation results of original system, an optimized conceptual design was proposed by the designers. The reliability analysis of the optimized system was performed. And the results indicated that the failure probability of the optimized design is reduced by two orders of magnitude and the optimized design is more reliable than the original design. This risk-informed approach can find the weakness in the conceptual design and guide the further design.
引用
收藏
页码:81 / 85
页数:5
相关论文
共 50 条
  • [31] Drop impact reliability testing for lead-free and lead-based soldered IC packages
    Chong, Desmond Y. R.
    Che, F. X.
    Pang, John H. L.
    Ng, Kellin
    Tan, Jane Y. N.
    Low, Patrick T. H.
    [J]. MICROELECTRONICS RELIABILITY, 2006, 46 (07) : 1160 - 1171
  • [32] Conceptual design and numerical assessment of compact heat exchanger for lead-based reactor
    Khan, Muhammad Salman
    Bai, Yunqing
    Chen, Zhibin
    Huang, Qunying
    Zou, Xiaoliang
    [J]. PROGRESS IN NUCLEAR ENERGY, 2020, 124
  • [33] Operation and control simulation of multi-modular lead-based reactor systems
    Yang, Xiao
    Zhao, Chengxuan
    Song, Yong
    Gao, Sheng
    Zhang, Junjun
    [J]. PROGRESS IN NUCLEAR ENERGY, 2021, 131
  • [34] Module coordination control of multi-modular lead-based reactor systems
    Yang, Xiao
    Zhao, Chengxuan
    Wang, Jianye
    Yu, Jie
    Yang, Minghan
    [J]. ANNALS OF NUCLEAR ENERGY, 2022, 168
  • [35] Conceptual design and optimization of power generation system for lead - based reactor
    Khan, Muhammad Salman
    Bai, Yunqing
    Huang, Qunying
    Xu, Chi
    Sun, Lujun
    Zou, Xiaoliang
    Wang, Lei
    [J]. APPLIED THERMAL ENGINEERING, 2020, 168
  • [36] Analysis and Simulation of a Gripper for Fuel Handling on China Lead-Based Research Reactor
    Zeng, Meihua
    Song, Yong
    Bai, Yunqing
    Wang, Minghuang
    He, Meisheng
    Yu, Jie
    [J]. NUCLEAR TECHNOLOGY, 2018, 204 (02) : 238 - 247
  • [37] Code development on steady-state thermal-hydraulic for small modular natural circulation lead-based fast reactor
    Zhao, Pengcheng
    Liu, Zijing
    Yu, Tao
    Xie, Jinsen
    Chen, Zhenping
    Shen, Chong
    [J]. NUCLEAR ENGINEERING AND TECHNOLOGY, 2020, 52 (12) : 2789 - 2802
  • [38] Thermodynamic Analysis of Combined Cooling Heating and Power System with Absorption Heat Pump Based on Small Modular Lead-based Reactor
    Wang, Han
    Yu, Dali
    Xu, Chi
    Khan, Muhammad Salman
    Bai, Yunqing
    [J]. 2021 5TH INTERNATIONAL CONFERENCE ON ADVANCES IN ENERGY, ENVIRONMENT AND CHEMICAL SCIENCE (AEECS 2021), 2021, 245
  • [39] Neutronics and thermal-hydraulics coupling analysis for a small lead-based fast reactor based on the discrete ordinate nodal and parallel channel method
    Fang, Chao
    Peng, Xingjie
    Zhao, Chen
    Lou, Lei
    Zhang, Bin
    Wang, Lianjie
    Chen, Zhang
    Li, Qing
    [J]. FRONTIERS IN ENERGY RESEARCH, 2023, 11
  • [40] Research on Core Power Control of Small Lead-based Reactor Based on Ant Colony Algorithm
    Li, Jinyang
    Liu, Yinuo
    Zeng, Wenjie
    Hu, Yang
    Yu, Tao
    [J]. Hedongli Gongcheng/Nuclear Power Engineering, 2022, 43 (03): : 135 - 138