Demonstration of leak-before-break in Japan Sodium cooled Fast Reactor (JS']JSFR) pipes

被引:12
作者
Wakai, Takashi [1 ]
Machida, Hideo [2 ]
Yoshida, Shinji [2 ]
Xu, Yang [3 ]
Tsukimori, Kazuyuki [1 ]
机构
[1] Japan Atom Energy Agcy, Oarai, Ibaraki 3111393, Japan
[2] TEPCO Syst Corp, Koto Ku, Tokyo 1350034, Japan
[3] Mitsubishi FBR Syst Inc, Shibuya Ku, Tokyo 1500001, Japan
关键词
Cracks;
D O I
10.1016/j.nucengdes.2013.08.012
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
This paper describes the leak-before-break (LBB) assessment procedure applicable to Japan Sodium cooled Fast Reactor (JSFR) pipes made of modified 9Cr-1Mo steel. For the sodium pipes of JSFR, the continuous leak monitoring will be adopted as an alternative to a volumetric test of the weld joints under conditions that satisfy LBB. Firstly, a LBB assessment flowchart eliminating uncertainty resulted from small scale leakage, such as self plugging phenomenon and influence of crack surface roughness on leak rate, was proposed. Secondly, a rational unstable fracture assessment technique, taking the compliance changing with crack extension into account, was also proposed. Thirdly, a crack opening displacement (COD) assessment technique was developed, because COD assessment method applicable to JSFR pipes - thin wall and small work hardening material - had not been proposed yet. In addition, fracture toughness tests were performed using compact tension (CT) specimens to obtain the fracture toughness, J(IC) and the crack growth resistance (J-R) curve at elevated temperature. Finally, by using the flowchart, proposed techniques and collected data, LBB assessment for the primary sodium pipes of JSFR was conducted. As a result, LBB aspect was successfully demonstrated with sufficient margins. (C) 2013 Elsevier B.V. All rights reserved.
引用
收藏
页码:88 / 96
页数:9
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