Aging State Analysis of Safety-related Cables for Nuclear Power Plants Exposed to Simulated Accident Conditions

被引:0
|
作者
Minakawa, Takefumi [1 ,2 ]
Ikeda, Masaaki [1 ]
Hirai, Naoshi [3 ]
Ohki, Yoshimichi [2 ,3 ,4 ]
机构
[1] Secretariat Nucl Regulat Author SNRAR, Regulatory Stand & Res Dept, Tokyo, Japan
[2] Waseda Univ, Cooperat Major Nucl Energy, Tokyo, Japan
[3] Waseda Univ, Res Inst Mat Sci & Technol, Tokyo, Japan
[4] Waseda Univ, Dept Elect Engn & Biosci, Minato Ku, 1-9-9 Roppongi, Tokyo 1068450, Japan
关键词
SILICONE-RUBBER; DEGRADATION;
D O I
暂无
中图分类号
TM [电工技术]; TN [电子技术、通信技术];
学科分类号
0808 ; 0809 ;
摘要
Several cables in safety-related systems in nuclear power plants are required to maintain their intended electrical insulating function while they are exposed to harsh environmental conditions in the primary containment vessel during assumed accidents. This must be satisfied even after the cables are operated for their full service period. For such cables, the behavior of their insulation under accidents is a matter of concern. In this research, after silicone rubber insulated cables were pre-aged by simultaneous thermal and radiation exposure, they were irradiated or exposed to high temperature steam to simulate the environmental conditions during the accident, or subjected to the combination of these conditions. The resultant changes in various properties were analyzed by instrumental analyses. As a result, it has been confirmed that the pre-aging and radiation exposure induce cross-linking and depolymerization of siloxane chains to produce cyclic siloxanes, whereas the steam exposure causes significant depolymerization and the generation of low-molecular cyclic siloxanes.
引用
收藏
页码:602 / 605
页数:4
相关论文
共 50 条
  • [41] THE SAFETY-RELATED PROPERTIES OF FUTURE HTR-MODULE POWER-PLANTS
    HUBEL, HJ
    LOHNERT, GH
    ATOMKERNENERGIE-KERNTECHNIK, 1985, 47 (03): : 159 - 162
  • [42] SEISMIC QUALIFICATION TESTS OF SAFETY-RELATED VALVES AND AIR DAMPERS FOR NUCLEAR POWER PLANTS (ACTIVE COMPONENTS TEST PROGRAM).
    Uchiyama, Y.
    Suzuki, S.
    Ichiki, T.
    Matsumoto, T.
    Saruyama, I.
    Komori, A.
    Hara, F.
    Irie, S.
    Transactions of the International Conference on Structural Mechanics in Reactor Technology, 1985, K
  • [43] Research and Application of Significance Determination for Safety-Related Feedback Information Based on Analytic Hierarchy Process in Nuclear Power Plants
    Zou X.
    Zhang H.
    Lei L.
    Xu Y.
    Zheng L.
    Jiao F.
    Hedongli Gongcheng/Nuclear Power Engineering, 2023, 44 (03): : 189 - 195
  • [44] QUALIFYING SAFETY-RELATED NUCLEAR-POWER PLANT ELECTRIC EQUIPMENT - DILEMMA
    CHIAPPETTA, CM
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1978, 30 (NOV): : 492 - 494
  • [45] SAFETY-RELATED TOPICS FROM THE NUCLEAR-POWER OPTIONS VIABILITY STUDY
    TRAUGER, DB
    WHITE, JD
    NUCLEAR SAFETY, 1986, 27 (04): : 467 - 475
  • [46] Managing Safety-Related Disruptions: Evidence from the US Nuclear Power Industry
    Blanco, Christian C.
    Caro, Felipe
    Corbett, Charles J.
    RISK ANALYSIS, 2019, 39 (10) : 2197 - 2213
  • [47] Aircraft impact analysis of nuclear safety-related concrete structures: A review
    Jiang, Hua
    Chorzepa, Mi G.
    ENGINEERING FAILURE ANALYSIS, 2014, 46 : 118 - 133
  • [48] ON THE IMPLEMENTATION OF DISTURBANCE ANALYSIS SYSTEMS FOR DETECTION AND DIAGNOSIS OF SAFETY-RELATED TRANSIENTS IN A NUCLEAR-POWER PLANT
    GUARRO, S
    OKRENT, D
    NUCLEAR ENGINEERING AND DESIGN, 1981, 65 (01) : 3 - 16
  • [49] Stability and steady state analysis of control and safety systems of Nuclear Power Plants
    Gupta, Brijendra
    Singh, Pooja
    Singh, Lalit
    ANNALS OF NUCLEAR ENERGY, 2020, 147
  • [50] Non-destructive diagnosis technique for aging of cables used at nuclear power plants
    Nishida, Y
    NUCLEAR ENGINEERING AND DESIGN, 2001, 207 (03) : 317 - 325