The effect of flow-accelerated corrosion with high-temperature sodium hydroxide on tube target-wastage caused in steam generator of sodium-cooled fast reactor

被引:0
|
作者
Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Higashi-ibaraki-gun, Ibaraki, 311-1393, Japan [1 ]
机构
来源
Nihon Kikai Gakkai Ronbunshu, B | 2013年 / 799卷 / 267-270期
关键词
D O I
10.1299/kikaib.79.267
中图分类号
学科分类号
摘要
Wastage phenomena on adjacent tubes (target-wastage) arise from water/steam leak in steam generators of sodium-cooled fast reactors. Target-wastage is likely to be caused by liquid droplet impingement erosion and flow-accelerated corrosion in an environment marked by high-temperature and high-alkali (reaction jet) due to sodium-water reaction. The static and flow-accelerated corrosion experiments have been carried out as a part of phenomena elucidation experiments for target-wastage by using actual tube material under high-temperature sodium-hydroxide and sodium monoxide conditions which are mainly generated by sodium-water reaction. The authors evaluated the dependence of liquid/tube material temperature and liquid velocity upon the flow-accelerated corrosion rate on the tube and derived the new correlation of flow-accelerated corrosion for target-wastage taking into account local wastage environment in this report. ©2013 The Japan Society of Mechanical Engineers.
引用
收藏
相关论文
共 35 条
  • [21] POWER-GENERATING UNIT WITH DUAL-LOOP SODIUM-COOLED FAST REACTOR AND DUAL-WALL STEAM GENERATOR
    Bagdasarov, Yu. E.
    Kamaev, A. A.
    [J]. ATOMIC ENERGY, 2009, 107 (03) : 155 - 161
  • [22] High temperature design and damage evaluation of a helical type sodium-to-air heat exchanger in a sodium-cooled fast reactor
    Hyeong-Yeon Lee
    Jae-Hyuk Eoh
    Yong-Bum Lee
    [J]. Journal of Mechanical Science and Technology, 2013, 27 : 2729 - 2735
  • [23] High temperature design and damage evaluation of a helical type sodium-to-air heat exchanger in a sodium-cooled fast reactor
    Lee, Hyeong-Yeon
    Eoh, Jae-Hyuk
    Lee, Yong-Bum
    [J]. JOURNAL OF MECHANICAL SCIENCE AND TECHNOLOGY, 2013, 27 (09) : 2729 - 2735
  • [24] Review of the finite element models for a structural integrity evaluation of the sodium-cooled fast reactor high temperature piping
    Park, Chang-Gyu
    Joo, Young-Sang
    Kim, Jong-Bum
    [J]. JOURNAL OF MECHANICAL SCIENCE AND TECHNOLOGY, 2012, 26 (09) : 2807 - 2813
  • [25] Review of the finite element models for a structural integrity evaluation of the sodium-cooled fast reactor high temperature piping
    Chang-Gyu Park
    Young-Sang Joo
    Jong-Bum Kim
    [J]. Journal of Mechanical Science and Technology, 2012, 26 : 2807 - 2813
  • [26] Development of High Temperature Electro-Magnetic Acoustic Transducer for In-Service Inspection of Reactor Vessel in Sodium-cooled Fast Reactor
    Kim, Hoe-Woong
    Park, Sang-Jin
    Son, Jin-Gwan
    Joo, Young-Sang
    Kim, Sung-Kyun
    Kim, Jong-Bum
    [J]. JOURNAL OF THE KOREAN SOCIETY FOR NONDESTRUCTIVE TESTING, 2018, 38 (04) : 225 - 231
  • [27] Physical characteristics and problems of developing a sodium-cooled fast reactor as a source of high-potential thermal energy for hydrogen production and other high-temperature technologies
    Poplavskii, V. M.
    Zabud'ko, A. N.
    Petrov, E. E.
    Ovcharenko, M. K.
    Popov, V. V.
    Bogush, V. B.
    Loginov, N. I.
    Tarasov, V. A.
    Polevoi, V. B.
    Khoromskii, V. A.
    Mikheev, A. S.
    [J]. ATOMIC ENERGY, 2009, 106 (03) : 162 - 167
  • [28] Physical characteristics and problems of developing a sodium-cooled fast reactor as a source of high-potential thermal energy for hydrogen production and other high-temperature technologies
    V. M. Poplavskii
    A. N. Zabud’ko
    É. E. Petrov
    M. K. Ovcharenko
    V. V. Popov
    V. B. Bogush
    N. I. Loginov
    V. A. Tarasov
    V. B. Polevoi
    V. A. Khoromskii
    A. S. Mikheev
    [J]. Atomic Energy, 2009, 106 : 162 - 167
  • [29] Time-dependent change in occurrence rate of steam generator tube leak in sodium-cooled fast reactors-Phenix and BN-600
    Kurisaka, Kenichi
    [J]. MECHANICAL ENGINEERING JOURNAL, 2024, 11 (02):
  • [30] Performance Improvement of High Temperature Electro-Magnetic Acoustic Transducer for In-service Inspection of Reactor Vessel in Sodium-cooled Fast Reactor
    Cho, Jae Hun
    Kim, Hoe-Woong
    Park, Sang-Jin
    Kim, Sung-Kyun
    [J]. JOURNAL OF THE KOREAN SOCIETY FOR NONDESTRUCTIVE TESTING, 2021, 41 (02) : 94 - 101