Role of residual ferrites on crevice SCC of austenitic stainless steels in PWR water with high-dissolved oxygen-Reference-Cited by-同舟云学术

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Role of residual ferrites on crevice SCC of austenitic stainless steels in PWR water with high-dissolved oxygen

Published:2020-11 Issue:11 Volume:52 Page:2552-2564
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Sinjlawi Abdullah,Chen Junjie,Kim Ho-Sub,Lee Hyeon Bae,Jang Changheui,Lee Sanghoon

Funder

Energy R&D Program

MOTIE/KETEP of the Republic of Korea

Engineering Research Center Program

Nuclear R&D Program

MSIT/NRF of the Republic of Korea

BK-Plus Program of the MSIT of the Republic of Korea

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference31 articles.

1. Effect of groove on socket welds under the condition of vibration fatigue;Xiu;J. Nucl. Mater.,2013

2. Vibration Fatigue Testing of Socket Welds (PWRMRP-07),1999

3. Socket weld integrity in nuclear piping under fatigue loading condition;Choi;Nucl. Eng. Des.,2007

4. Investigation of fatigue-induced socket-welded joint failures for small-bore piping used in power plants;Hopkins;Practical Fail. Anal.,2001

5. Vibration Fatgiue Testing of Socket Welds, Phase II;Hirschberg,1998

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1. Chloride-Induced Stress Corrosion Cracking of Friction Stir-Welded 304L Stainless Steel: Effect of Microstructure and Temperature;Crystals;2024-06-16

2. Synthesis of multi-phase steel thin films by a low energy plasma focus device;Materials Chemistry and Physics;2024-06

3. Determining SCC resistance of stainless steel claddings in high- temperature water by constant load crack growth tests and slow strain rate tests;Journal of Nuclear Materials;2024-01

4. Effects of composition and microstructure on oxidation and stress corrosion cracking susceptibility of stainless steel claddings in hydrogenated PWR primary water;Journal of Nuclear Materials;2021-09

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