An experience with in-service fabrication and inspection of austenitic stainless steel piping in high temperature sodium system

被引:1
|
作者
Ravi, S. [1 ]
Laha, K. [1 ]
Sakthy, S. [1 ]
Mathew, M. D. [1 ]
Bhaduri, A. K. [1 ]
机构
[1] Indira Gandhi Ctr Atom Res, Mech Met Div, Kalpakkam 603102, Tamil Nadu, India
关键词
D O I
10.1016/j.nucengdes.2014.12.034
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
A creep testing facility along with dynamic sodium loop was installed at Indira Gandhi Centre for Atomic Research, Kalpakkam, India to assess the creep behavior of fast reactor structural materials in flowing sodium. Type 304L austenitic stainless steel was used in the low cross section piping of hot-leg whereas 316LN austenitic stainless steel in the high cross section cold-leg of the sodium loop. The intended service life of the sodium loop was 10 years. The loop has performed successfully in the stipulated time period. To enhance its lifetime, it has been decided to replace the 304L piping with 316L piping in the hot-leg. There were more than 300 welding joints involved in the integration of cold-leg with the new 316L hot-leg. Continuous argon gas flow was maintained in the loop during welding to avoid contamination of sodium residue with air. Several innovative welding procedures have been adopted for joining the new hot-leg with the existing cold-leg in the presence of sodium residue adopting TIG welding technique. The joints were inspected for 100% X-ray radiography and qualified by performing tensile tests. The components used in the discarded hot-leg were retrieved, cleaned and integrated in the renovated loop. A method of cleaning component of sodium residue has been established. This paper highlights the in-service fabrication and inspection of the renovation. (C) 2015 Elsevier B.V. All rights reserved.
引用
收藏
页码:300 / 307
页数:8
相关论文
共 50 条
  • [21] STRENGTHENING OF AN AL-CONTAINING AUSTENITIC STAINLESS STEEL AT HIGH TEMPERATURE
    Dong, Xianping
    Zhao, Lin
    Sun, Feng
    Zhang, Lanting
    PROCEEDINGS OF THE ASME TURBO EXPO: TURBINE TECHNICAL CONFERENCE AND EXPOSITION, 2013, VOL 5A, 2013,
  • [22] Model of liquid gallium corrosion with austenitic stainless steel at a high temperature
    Shin, Sang Hun
    Kim, Seung Hyun
    Kim, Ji Hyun
    JOURNAL OF NUCLEAR MATERIALS, 2014, 450 (1-3) : 314 - 321
  • [23] EXPERIENCE WITH A LOW-ALLOYED FERRITIC STEEL FOR HIGH-TEMPERATURE SODIUM SERVICE
    GROSSER, D
    MAUSBECK, H
    STRAUBWA.W
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1970, 13 (01): : 109 - &
  • [24] Ultrasonic Transducers for In-Service Inspection and Continuous Monitoring in High-Temperature Environments
    Bouchy, Sevan
    Zednik, Ricardo J.
    Belanger, Pierre
    SENSORS, 2023, 23 (07)
  • [25] High Temperature Ultrasonic Transducers for In-Service Inspection of Liquid Metal Fast Reactors
    Griffin, J. W.
    Posakony, G. J.
    Harris, R. V.
    Baldwin, D. L.
    Jones, A. M.
    Bond, L. J.
    2011 IEEE INTERNATIONAL ULTRASONICS SYMPOSIUM (IUS), 2011, : 1924 - 1927
  • [26] Similitude study of an in-service industrial piping system under high flow induced vibration
    Yap Huey Tyng
    Ong Zhi Chao
    Kong Keen Kuan
    Zubaidah Ismail
    Abdul Ghaffar Abdul Rahman
    Chong Wen Tong
    Journal of Mechanical Science and Technology, 2017, 31 : 3705 - 3713
  • [27] Similitude study of an in-service industrial piping system under high flow induced vibration
    Tyng, Yap Huey
    Chao, Ong Zhi
    Kuan, Kong Keen
    Ismail, Zubaidah
    Rahman, Abdul Ghaffar Abdul
    Tong, Chong Wen
    JOURNAL OF MECHANICAL SCIENCE AND TECHNOLOGY, 2017, 31 (08) : 3705 - 3713
  • [28] HIGH TEMPERATURE OXIDATION BEHAVIOR OF AUSTENITIC STAINLESS STEEL WITH HIGH SILICON CONTENT.
    Fukase, Yukishige
    Nemoto, Rikio
    Tetsu-To-Hagane/Journal of the Iron and Steel Institute of Japan, 1977, 63 (05): : 688 - 699
  • [29] A study on corrosion behavior of austenitic stainless steel in liquid metals at high temperature
    Shin, Sang Hun
    Kim, Jong Jin
    Jung, Ju Ang
    Choi, Kyoung Joon
    Bang, In Cheol
    Kim, Ji Hyun
    JOURNAL OF NUCLEAR MATERIALS, 2012, 422 (1-3) : 92 - 102
  • [30] Application of in-service temperature lowering to reduce radioactivity corrosion product deposition on carbon steel piping of BWR residual heat removal system
    Aizawa, M
    Chiba, Y
    Ohsumi, K
    Uchida, S
    Takahashi, T
    Saitoh, T
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2002, 39 (10) : 1051 - 1059