Reliability Analysis for the Reactor Protection System of HTR-PM

被引:0
|
作者
Zhou, Shuqiao [1 ]
Guo, Chao [1 ]
Li, Duo [1 ]
机构
[1] Tsinghua Univ, Minist Educ, Key Lab Adv Reactor Engn & Safety, Inst Nucl & New Energy Technol,Collaborat Innovat, Beijing, Peoples R China
关键词
reactor protection system; reliability; Markov chain; optimal surveillance test interval;
D O I
暂无
中图分类号
TP301 [理论、方法];
学科分类号
081202 ;
摘要
A high-temperature gas-cooled reactor-pebble bed module (HTR-PM), as a demonstration nuclear power plant (NPP), is now under construction in the Shandong province of China. The reactor protection system (RPS) in an HTR-PM is a safety-related system and is mainly in charge of monitoring safety-related parameters according to the reactor protection requirements. Thus, an RPS is very important to operations during the entire life cycle of an NPP. An RPS for an HTR-PM is completely designed and developed in China, which owns all intellectual property rights. Traditionally, the reliability of an RPS is evaluated based on a failure mode, effects, and criticality analysis (FMECA) and a fault tree analysis (FTA), which are static methods and cannot reflect the reliability of the system's dynamics. In this paper, we propose a dynamic reliability model for the RPS in an HTR-PM based on the Markov chain theory. Using this model, all states and their dynamic transition processes, especially the degradation process from a 2-out-of-4 structure to a 2-out-of-3 structure, are all determined. Moreover, based on this proposed model, an optimal surveillance test interval can be determined.
引用
收藏
页数:6
相关论文
共 50 条
  • [21] Coordinated control system design and verification of HTR-PM plant
    Dong, Zhe
    Pan, Yifei
    Huang, Xiaojin
    Dong, Yujie
    Zhang, Zuoyi
    NUCLEAR ENGINEERING AND DESIGN, 2018, 329 : 25 - 33
  • [22] China First criticality for HTR-PM
    不详
    NUCLEAR ENGINEERING INTERNATIONAL, 2021, 66 (807): : 6 - 10
  • [23] DESIGN OF THE PROCESS AND EFFLUENT RADIATION MONITORING SYSTEM OF HTR-PM
    Xie, Feng
    Li, Wenqian
    Li, Zhihui
    Cao, Jianzhu
    Li, Hong
    Tong, Jiejuan
    Wang, Haitao
    PROCEEDINGS OF THE 24TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2016, VOL 1, 2016,
  • [24] HTR-PM fuel pebble irradiation qualification in the high flux reactor in Petten
    Knol, S.
    de Groot, S.
    Salama, R. V.
    Best, J.
    Bakker, K.
    Bobeldijk, I.
    Westlake, J. R.
    Futterer, M. A.
    Laurie, M.
    Tang, Chunhe
    Liu, Rongzheng
    Liu, Bing
    Zhao, Hongsheng
    NUCLEAR ENGINEERING AND DESIGN, 2018, 329 : 82 - 88
  • [25] Thermal-hydraulic feasibility analysis on uprating the HTR-PM
    Dong, YJ
    Gao, ZY
    NUCLEAR ENGINEERING AND DESIGN, 2006, 236 (5-6) : 510 - 515
  • [26] SAFETY ANALYSIS FOR HOT GAS DUCT VESSEL IN HTR-PM
    Li, Xiaotian
    Li, Xiaowei
    Shi, Li
    Zhang, Zhengming
    He, Shuyan
    NUCLEAR TECHNOLOGY, 2011, 174 (01) : 29 - 40
  • [27] Physical Analysis of the Initial Core and Running-In Phase for Pebble-Bed Reactor HTR-PM
    Zhang, Jingyu
    Li, Fu
    Sun, Yuliang
    SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2017, 2017
  • [28] Diversity analysis of htr reactor trip protection system
    Xu Z.
    Xue F.
    Gao Q.-Y.
    Na F.-L.
    1600, Atomic Energy Press (51): : 2344 - 2351
  • [29] Research on the Computed Tomography Pebble Flow Detecting System for HTR-PM
    Wan, Xin
    Liu, Ximing
    Miao, Jichen
    Cong, Peng
    Zhang, Yuai
    Wu, Zhifang
    SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2017, 2017
  • [30] RADIATION SHIELDING DESIGN OF HIGH TEMPERATURE REACTOR PEBBLE BED MODULE (HTR-PM)
    Sun, Sida
    Fang, Sheng
    Li, Hong
    PROCEEDINGS OF THE 24TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2016, VOL 4, 2016,