Risk-informed design optimization method and application in a lead-based research reactor

被引:0
|
作者
Wang, Jiaqun [1 ]
Wang, Qianglong [1 ,2 ]
Qiu, Jinrong [1 ]
Wang, Jin [3 ]
Wang, Fang [3 ]
Li, Yazhou [3 ]
机构
[1] Wuhan 2nd Ship Design & Res Inst, Wuhan 430064, Hubei, Peoples R China
[2] Xi An Jiao Tong Univ, Xian 710049, Shanxi, Peoples R China
[3] Int Acad Neutron Sci, Qingdao 266199, Shandong, Peoples R China
基金
中国国家自然科学基金;
关键词
Risk-informed design; Probabilistic safety assessment; Lead-based research reactor; RiskA; PROBABILISTIC SAFETY ASSESSMENT; TEST BLANKET MODULE; CONCEPTUAL DESIGN; DEVELOPMENT STRATEGY; PROGRESS; SYSTEM;
D O I
10.1016/j.net.2023.03.005
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Risk-informed approach has been widely applied in the safety design, regulation, and operation of nuclear reactors. It has been commonly accepted that risk-informed design optimization should be used in the innovative reactor designs to make nuclear system highly safe and reliable. In spite of the riskinformed approach has been used in some advanced nuclear reactors designs, such as Westinghouse IRIS, Gen-IV sodium fast reactors and lead-based fast reactors, the process of risk-informed design of nuclear reactors is hardly to carry out when passive system reliability should be integrated in the framework. A practical method for new passive safety reactors based on probabilistic safety assessment (PSA) and passive system reliability analyze linking is proposed in this paper. New three-dimension frequency-consequence curve based on risk concept with three variables is used in this method. The proposed method has been applied to the determination optimization of design options selection in a 10 MWth lead-based research reactor(LR) to obtain one optimized system design in conceptual design stage, using the integrated reliability and probabilistic safety assessment program RiskA, and the computation resources and time consumption in this process was demonstrated reasonable and acceptable.(c) 2023 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).
引用
收藏
页码:2047 / 2052
页数:6
相关论文
共 50 条
  • [21] Risk-informed integrated design optimization for offshore wind farm electrical systems
    Liu, Min
    Lu, Da-Gang
    Qin, Jianjun
    Miao, Yi-Zhi
    Zhang, Wei-Heng
    Zhu, Jiang-Sheng
    Faber, Michael Havbro
    [J]. RELIABILITY ENGINEERING & SYSTEM SAFETY, 2024, 250
  • [22] Application of risk-informed design methods to select the PSACS ultimate heat sink
    Elliott, Michael A.
    Apostolakis, George E.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2009, 239 (12) : 2654 - 2659
  • [23] Risk-Informed Design of Hybrid I&C Architectures for Research Reactors
    Rahman, Khalil Ur
    Jin, Kyungho
    Heo, Gyunyoung
    [J]. IEEE TRANSACTIONS ON NUCLEAR SCIENCE, 2016, 63 (01) : 351 - 358
  • [24] Risk-informed approach to the safety improvement of the reactor protection system of the AGN-201K research reactor
    Ahmed, Ibrahim
    Zio, Enrico
    Heo, Gyunyoung
    [J]. NUCLEAR ENGINEERING AND TECHNOLOGY, 2020, 52 (04) : 764 - 775
  • [25] Research on level 1 PSA and risk-informed design for ACP100
    Deng, Jian
    Xu, Youyou
    Qiu, Zhifang
    Zhang, Hang
    Wu, Lingjun
    Wang, Xiaoji
    Peng, Huanhuan
    Du, Zhengyu
    [J]. ANNALS OF NUCLEAR ENERGY, 2020, 144
  • [26] Risk-informed inspection of the Browns Ferry boiling water reactor
    Phillips, JH
    Graybeal, MR
    Victory, LJ
    [J]. INTERNATIONAL CONFERENCE ON ASSURING IT'S SAFE: INTEGRATING STRUCTURAL INTEGRITY, INSPECTION, AND MONITORING INTO SAFETY AND RISK ASSESSMENT, 1998, 1998 (06): : 259 - 263
  • [27] Conceptual Design Optimization of Uranium-zirconium Alloy Fuel Core for Modular Lead-based Fast Reactor
    Lou, Lei
    Wang, Lianjie
    Chen, Chang
    Zhao, Chen
    Zhou, Bingyan
    Yan, Mingyu
    Ma, Dangwei
    [J]. Hedongli Gongcheng/Nuclear Power Engineering, 2023, 44 (06): : 1 - 8
  • [28] 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
  • [29] 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
  • [30] Risk-informed portfolio assessment: Application to aviation safety
    Sharma, V.
    Coit, D. W.
    Luxhoj, J. T.
    [J]. RISK, RELIABILITY AND SOCIETAL SAFETY, VOLS 1-3: VOL 1: SPECIALISATION TOPICS; VOL 2: THEMATIC TOPICS; VOL 3: APPLICATIONS TOPICS, 2007, : 1407 - 1414