Evaluation of the thermal ageing of austenitic stainless steel welds with 10 % of δ-ferrites

Author:

Hong Sunghoon,Kim Hyunmyung,Kong Byeong Seo,Jang Changheui,Shin In Hwan,Yang Jun-Seog,Lee Kyoung-Soo

Funder

Korea Hydro

Nuclear Power Co., Ltd

MSIP/NRF of Rep. of Korea

MSIP/NRF of Korea

MSIP of Rep. of Korea

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference28 articles.

1. Control of Ferrite Content in Stainless Steel Weld Metal. Regulatory Guide 1.31, Revision 0 ∼ 4;U.S. Nuclear Regulatory Commission,1973

2. Embrittlement of laboratory and reactor aged CF3, CF8, and CF8M duplex stainless steels;Chung;Mater. Sci. Technol.,1990

3. Methodology for estimating thermal and neutron embrittlement of cast austenitic stainless steels during service in light water reactors;Chopra;J. Pressure Vessel Technol.,2016

4. Evaluation of thermal aging embrittlement in CF8 duplex stainless steel by small punch test;Cheon;J. Nucl. Mater.,2000

5. Evaluation of the recovery of thermal aging embrittlement of CF8M cast stainless steels after reversion heat treatments;Jang;Int. J. Pres. Ves. Pip.,2015

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