Comparison of oxide layers formed on the low-cycle fatigue crack surfaces of Alloy 690 and 316 SS tested in a simulated PWR environment

Author:

Chen Junjie,Nurrochman Andrieanto,Hong Jong-Dae,Kim Tae Soon,Jang Changheui,Yi Yongsun

Funder

Korea Hydro and Nuclear Power Co., Ltd

KUSTAR-KAIST

MSIP/NRF

MSIP of the Republic of Korea

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference36 articles.

1. Corrosion in pressurized water reactors (PWRs);Couvant,2013

2. Materials challenges for nuclear systems;Allen;Mater. Today,2010

3. Final proposal of environmental fatigue life correction factor (Fen);Higuchi,2007

4. Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials, NUREG/CR-6909 draft Rev.1;Chopra,2014

5. Environmental fatigue of metallic materials in nuclear power plants – a review of Korean test programs;Jang;Nucl. Eng. Technol.,2013

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