Probabilistic safety assessment method for spent nuclear fuel road transportation

被引:12
作者
Tao, Longlong [1 ,2 ]
Wang, Jin [1 ]
Long, Pengcheng [1 ]
Wang, Dagui [1 ]
Wang, Fang [1 ]
Zhou, Baichang [3 ]
Chen, Jun [3 ]
机构
[1] Chinese Acad Sci, Inst Nucl Energy Safety Technol, Key Lab Neutron & Radiat Safety, Hefei 230031, Anhui, Peoples R China
[2] Univ Sci & Technol China, Hefei 230027, Anhui, Peoples R China
[3] PLA, Unit 96901, Sect 23, Beijing 100095, Peoples R China
基金
中国国家自然科学基金;
关键词
RiskA; Spent nuclear fuel transportation; Risk analysis; Probabilistic safety assessment; PVCRES; RISK-ASSESSMENT;
D O I
10.1016/j.anucene.2019.107043
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
Spent Nuclear Fuel (SNF) transportation has the potential possibility of releasing radioactivity, thus it is significant to assess the transportation risks and take effective measures to improve its safety. Current researches were mainly focused on the assessment of the transportation consequences, which lacked detailed and systematic analysis of the transportation process. In this paper, Probabilistic Safety Assessment (PSA) method for SNF Road Transportation (SNFRT) is proposed. The PVCRES (personnel, vehicle, cask, road, environment, supervision and management) risk indicators are proposed and quantified to characterize the risks that exist during the transportation process, which is in line with the actual situation. Then an ET/FT integrated model is established in order to assess the risk of SNFRT process from a certain Nuclear Power Plant (NPP) to the reprocessing plant. The risk level is quantified and targeted improvement approaches are proposed to demonstrate the feasibility and effectiveness of this method. (C) 2019 Elsevier Ltd. All rights reserved.
引用
收藏
页数:8
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