Irradiation assisted stress corrosion cracking of 347 stainless steel in simulated PWR primary water containing lithium hydroxide or potassium hydroxide-Reference-Cited by-同舟云学术

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Irradiation assisted stress corrosion cracking of 347 stainless steel in simulated PWR primary water containing lithium hydroxide or potassium hydroxide

Published:2023-12 Issue: Volume:586 Page:154676
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Sinjlawi Abdullah S.^ORCID,Dong Lijin^ORCID,Ickes Mickael,Sun Kai,Was Gary S.^ORCID

Funder

US Department of Energy Office of Nuclear Energy

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference38 articles.

1. Managing Critical Isotopes: Stewardship of Lithium-7 is Needed to Ensure a Stable Supply,2013

2. Investigation on core basket bolts from a VVER 440 power plant;Ehrnsten,2015

3. Irradiation assisted stress corrosion cracking of austenitic stainless steel in WWER reactor core internals;Hojna,2015

4. Effect of Boron Concentration On Alloy-690 Corrosion Product Release Rates - Results at 325°C and 285°C, EPRI report 1011744, 2005.

5. Evaluation of Stress Corrosion Cracking Behavior of Ni-Base Alloys in PWR Primary Water Containing KOH vs;Zhai,2021

Cited by 2 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. How irradiation promotes intergranular stress corrosion crack initiation;Progress in Materials Science;2024-06

2. Corrosion of Stainless Steel in Simulated Nuclear Reactor Primary Coolant—Experiments and Modeling;Materials;2024-03-01

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