Fracture mechanics evaluation of cast duplex stainless steel after thermal aging

被引:16
|
作者
Tujikura, Y [1 ]
Urata, S [1 ]
机构
[1] Kansai Elect Power Co Inc, Gen Off Nucl & Fossil Power Prod, Kita Ku, Osaka 5308270, Japan
关键词
D O I
10.1016/S0029-5493(99)00147-8
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
For the primary coolant piping of PWRs in Japan, cast duplex stainless steel, which is excellent in terms of strength, corrosion resistance and weldability, has conventionally been used. Cast duplex stainless steel contains the ferrite phase in the austenite matrix, and thermal aging after long-term service is known to decrease fracture toughness. Therefore, we evaluated the integrity of the primary coolant piping for an initial PWR plant in Japan by means of elastic plastic fracture mechanics. The evaluation results show that the crack will not grow into an unstable fracture and the integrity of the piping will be secure, even when such through-wall crack length is assumed to be as large as the fatigue crack length grown for a service period of up to 60 years. (C) 1999 Elsevier Science S.A. All rights reserved.
引用
收藏
页码:255 / 261
页数:7
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