Accelerating Test Method of Thermal Aging for High Heat Generating Equipment in Nuclear Power Plant

被引:0
|
作者
Lim, Byung-Ju [1 ]
Park, Chang-Dae [1 ]
Chung, Kyung-Yul [1 ]
机构
[1] Korea Inst Machinery & Mat, Environm & Energy Syst Res Div, 171 Jangdong, Daejeon, South Korea
关键词
D O I
暂无
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
In nuclear power plant, the electrical equipment which is qualified by procedures and rules of IEEE standard performs accident condition test after aging in many normal conditions of heat, radiation, mechanical and vibration. Because install life of the equipment is over 10 or 20 years, the accelerating aging test is applied for normal aging test. Especially in thermal aging test, Arrhenius equation, which defines relationship between activation energy of a material and chemical reaction rate, is used as a tool calculating the accelerated condition of the test. The equation enables to easily convert actual operating temperature in a long time into accelerated test condition with higher temperature of shortened period. However, temperature of components of the electric equipment often increases by heat sources such as power supply, electrical circuit and coil. This heat-rise makes difficulty for deciding the accelerated condition of thermal aging test. In addition, the number of components composing of the equipment and various temperatures of each component are an additional consideration of the difficulty. We proposed the effective method and technology of accelerated thermal aging test for heat-rise equipment in NPP and verified that the method could suggest the reasonable accelerating condition.
引用
收藏
页数:5
相关论文
共 50 条
  • [1] Evaluation of thermal aging effect on primary pipe material in nuclear power plant by micro hardness test method
    Xue, Fei
    Yu, Wei-Wei
    Wang, Zhao-Xi
    Ma, Qin-Zheng
    Liu, Wei
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2012, 46 (07): : 809 - 814
  • [2] A METHOD FOR INSITU TEST AND ANALYSIS OF NUCLEAR-PLANT EQUIPMENT
    UNRUH, JF
    POLCH, EZ
    KANA, DD
    JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 1984, 106 (04): : 369 - 374
  • [4] SEISMIC STABILITY OF POWER GENERATING EQUIPMENT (SUBJECT SELECTION). SUBSTANTIATION OF SEISMIC STABILITY OF NUCLEAR POWER PLANT EQUIPMENT BY CALCULATION.
    Avdeev, V.I.
    Bazilevskii, S.V.
    Panasenko, N.N.
    Zadai, A.R.
    Kravchenko, N.V.
    Pukhov, V.G.
    Soviet energy technology, 1987, (09): : 36 - 43
  • [5] Seismic proving test of equipment and structures in thermal conventional power plant
    Tazuke, H
    Yamaguchi, S
    Ishida, K
    Sakurai, T
    Akiyama, H
    Chiba, T
    JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2002, 124 (02): : 133 - 143
  • [6] Criteria for Thermal Efficiency of Combined Heat and Power and Nuclear Power Plants Generating Electrical and Thermal Energy
    Smolkin, Yu. V.
    Kruglikov, P.A.
    Kulakov, E.N.
    Sobolev, D.A.
    Stepanov, D.V.
    Popov, A.V.
    Power Technology and Engineering, 2024, 58 (04) : 639 - 643
  • [7] Method on the aging evaluation in nuclear power plant concrete structures
    Kitsutaka, Yoshinori
    Tsukagoshi, Masayuki
    NUCLEAR ENGINEERING AND DESIGN, 2014, 269 : 286 - 290
  • [8] Thermal aging study of PEEK for nuclear power plant containment dome
    Cuimiao Zhu
    Haisong Zhang
    Jianxi Li
    Journal of Polymer Research, 2022, 29
  • [9] Thermal aging study of PEEK for nuclear power plant containment dome
    Zhu, Cuimiao
    Zhang, Haisong
    Li, Jianxi
    JOURNAL OF POLYMER RESEARCH, 2022, 29 (01)
  • [10] Risk Assessment of Test Cycle Change of Important Equipment in Nuclear Power Plant
    Yu, Xipeng
    Dai, Hongwei
    2024 6TH ASIA ENERGY AND ELECTRICAL ENGINEERING SYMPOSIUM, AEEES 2024, 2024, : 378 - 382