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
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页码:300 / 307
页数:8
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