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
  • [1] Evaluation of the thermal aging effect on Charpy impact properties of the primary pipe material in nuclear power station
    Xue, Fei
    Shu, Guo-Gang
    Yu, Wei-Wei
    Wang, Zhao-Xi
    Meng, Xin-Ming
    Ti, Wen-Xin
    Gongcheng Lixue/Engineering Mechanics, 2010, 27 (08): : 246 - 250
  • [2] Thermal aging embrittlement evaluation of nuclear primary pipe steel by ductile to brittle transition test
    Xue, Fei
    Yu, Weiwei
    Wang, Zhaoxi
    Shu, Guogang
    Wang, Xitao
    Jiang, Jiawang
    MANUFACTURING SCIENCE AND ENGINEERING, PTS 1-5, 2010, 97-101 : 797 - +
  • [3] Accelerating Test Method of Thermal Aging for High Heat Generating Equipment in Nuclear Power Plant
    Lim, Byung-Ju
    Park, Chang-Dae
    Chung, Kyung-Yul
    22ND INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2013), 2013,
  • [4] Method on the aging evaluation in nuclear power plant concrete structures
    Kitsutaka, Yoshinori
    Tsukagoshi, Masayuki
    NUCLEAR ENGINEERING AND DESIGN, 2014, 269 : 286 - 290
  • [5] EFFECT OF VERTICAL PIPE LENGTH ON THE THERMAL STRATIFICATION IN NUCLEAR POWER PLANT SURGELINE
    Kim, Young-Jong
    Kim, Maan-Won
    Lee, Hyun-Soon
    Ko, Eunmi
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, VOL 4, 2009, : 59 - 64
  • [6] Tensile and low cycle fatigue behavior of primary pipe material for PWR nuclear power plant
    Xue, Fei
    Shu, Guogang
    Yu, WeiWei
    Ti, Wenxin
    Lin, Lei
    Shi, Chongzhe
    EVALUATION, INSPECTION AND MONITORING OF STRUCTURAL INTEGRITY, 2008, : 293 - 298
  • [7] THERMAL AGING EFFECT OF CDSS ON THE INTEGRITY OF THE PWR PRIMARY PIPE WITH DAMAGE TOLERANCE METHOD
    Wang Zhao-Xi
    Xue Fei
    Shi Hui-Ji
    Yu Wei-Wei
    Shu Guo-Gang
    PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING 2010, VOL 5, 2011, : 141 - 145
  • [8] Aseismic evaluation for aging degradation of nuclear power plant components
    Nuclear Power Engineering Department, Tokyo Electric Power Company, 1-1-3 Uchi-saiwaicho, Chiyada, Tokyo 100-0011, Japan
    Nucl Eng Des, 1600, 1-2 (57-71):
  • [9] Aging evaluation of fuse holders of BWR nuclear power plant
    Armenta-Molina, Alejandra
    Hernandez-Gomez, Luis Hector
    Pascual-Hernandez, Carlos Daniel
    Villasenor-Chavez, Daniel
    Soto-Mendoza, Gilberto
    Perez-Escobar, Brayan Leonardo
    Arreola-Valles, Tanya Nerina
    Perez-Montejo, Salatiel
    RESULTS IN ENGINEERING, 2024, 24
  • [10] Aseismic evaluation for aging degradation of nuclear power plant components
    Kobayashi, K
    NUCLEAR ENGINEERING AND DESIGN, 2002, 214 (1-2) : 57 - 71
12345