J-R fracture properties of SA508-1a ferritic steels and SA312-TP347 austenitic steels for pressurized water reactor's (PWR) primary coolant piping

被引：22

作者：

Lee, BS ^{[1
]}

Oh, YJ ^{[1
]}

Yoon, JH ^{[1
]}

Kuk, IH ^{[1
]}

Hong, JH ^{[1
]}

机构：

[1] Korea Atom Energy Res Inst, Div Nucl Mat Technol, Taejon 305600, South Korea

来源：

NUCLEAR ENGINEERING AND DESIGN | 2000年 / 199卷 / 1-2期

关键词：

D O I：

10.1016/S0029-5493(99)00061-8

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：

J-R fracture resistance of SA508-1a and SA312-TP347 steels, which are both rather peculiar as PWR primary coolant piping materials, were evaluated for application of leak-before-break methodology to the design basis of nuclear power plant piping. Archive materials from various heats of both steel pipes showed apparent heat-to-heat variations in ductile fracture resistance at the operating temperature 316 degrees C. The SA508-1a ferritic steels showed relatively good J-R curve properties although they varied with the microstructures depending on the manufacturing process and chemical compositions. On the other hand, ductile crack growth resistance of SA312-TP347 austenitic stainless steel was unexpectedly poor when carbon content is moderately high. It was found that coarse niobium carbides deteriorated the ductile fracture resistance, so that more rigorous specification is needed in carbon and niobium contents to improve fracture properties of Type 347 stainless steels. (C) 2000 Elsevier Science S.A. All rights reserved.

引用

页码：113 / 123

页数：11

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