Evaluation of thermal aging effect on primary pipe material in nuclear power plant by micro hardness test method

被引：0
|
作者：
Xue, Fei [1 ,2 ]
Yu, Wei-Wei [2 ]
Wang, Zhao-Xi [2 ]
Ma, Qin-Zheng [2 ]
Liu, Wei [1 ]
机构：
[1] Department of Materials Science and Engineering, Tsinghua University, Beijing 100084, China
[2] Suzhou Nuclear Power Research Institute, Suzhou 215004, China
来源：
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2012年 / 46卷 / 07期
关键词：
D O I：
暂无
中图分类号：
学科分类号：
摘要：
18
引用
收藏
页码：809 / 814
相关论文
共 50 条
  • [41] Evaluation of a new gamma emission imaging system and method for nuclear waste in nuclear power plant environments
    Joung, J.
    Hung, M.
    Kim, Y.
    Bae, K.
    Park, J. M.
    Kim, K. Y.
    Lim, J. W.
    2018 IEEE NUCLEAR SCIENCE SYMPOSIUM AND MEDICAL IMAGING CONFERENCE PROCEEDINGS (NSS/MIC), 2018,
  • [42] Golden section method for evaluation of electric and thermal power tariff at thermoelectric plant
    Khlebalin, Yu.M.
    Promyshlennaya Energetika, 2001, (09): : 9 - 14
  • [43] A study on characteristics and internal exposure evaluation of radioactive aerosols during pipe cutting in decommissioning of nuclear power plant
    Kim, Sun Il
    Lee, Hak Yun
    Song, Jong Soon
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2018, 50 (07) : 1088 - 1098
  • [44] Diagnosing nuclear power plant pipe wall thinning due to flow accelerated corrosion using a passive, thermal non-destructive evaluation method: Feasibility assessment via numerical experiments
    Nash, Chris
    Karve, Pranav
    Adams, Douglas
    NUCLEAR ENGINEERING AND DESIGN, 2022, 386
  • [45] AGING EVALUATION FOR THE EXTENSION OF QUALIFIED LIFE OF NUCLEAR POWER PLANT EQUIPMENT THROUGH MODULATED POISSON PROCESSES
    Saldanha, Pedro L. C.
    Frutuoso e Melo, P. F.
    ICONE 17: PROCEEDINGS OF THE 17TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 1, 2009, : 89 - 97
  • [46] SEISMIC TEST ANALYSIS EVALUATION OF MOTOR-OPERATED VALVE ACTUATORS FOR NUCLEAR POWER PLANT
    Kojima, Nobuo
    Tsutsumi, Yoshitaka
    Yonekura, Kazuyoshi
    Nishino, Koji
    Watanabe, Yukio
    Kumagai, Shin
    Kamino, Hiroyuki
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2018, VOL 8, 2019,
  • [47] Material damage evaluation of primary power plant components using sub-size specimens
    Lucon, E
    ADVANCED ENGINEERING MATERIALS, 2001, 3 (05) : 291 - 302
  • [48] THE HOT TEST OF PRIMARY SEPERATION EQUIPMENT OF STEAM GENERATOR FOR CAP1400 NUCLEAR POWER PLANT
    Ying Bingbin
    Li Xilin
    Zhang Feixi
    Lin Shaoxuan
    PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 2, 2017,
  • [49] Development of a web-based integrity evaluation system for primary components in a nuclear power plant
    Lee, SM
    Kim, JC
    Choi, JB
    Kim, YJ
    Choi, SN
    Jang, KS
    Hong, SY
    ADVANCES IN NONDESTRUCTIVE EVALUATION, PT 1-3, 2004, 270-273 : 2226 - 2231
  • [50] Evaluation of the effect of thermal oxygen aging on base and SBS-modified bitumen at micro and macroscales
    Li, Chao
    Xie, Xiaofeng
    Wang, Lan
    Guo, Yingying
    Zhang, Le
    Xue, Zhihua
    CONSTRUCTION AND BUILDING MATERIALS, 2022, 324
12345