Microstructure response and sodium corrosion behavior of ferritic-martensitic steel after proton irradiation-Reference-Cited by-同舟云学术

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Microstructure response and sodium corrosion behavior of ferritic-martensitic steel after proton irradiation

Published:2024-07 Issue: Volume: Page:
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Lee Jeonghyeon,Kim Taeho,Kim Taeyong,Kim Ji Hyun^ORCID

Publisher

Elsevier BV

Reference44 articles.

1. Model of liquid gallium corrosion with austenitic stainless steel at a high temperature;Shin;J. Nucl. Mater.,2014

2. Dissolution corrosion of 316L austenitic stainless steels in contact with static liquid lead-bismuth eutectic (LBE) at 500 °C;Lambrinou;J. Nucl. Mater.,2017

3. Requirement of decontamination factor for near-surface disposal of PEACER wastes;Kim;Prog. Nucl. Energy,2007

4. Comparison of sodium and lead-cooled fast reactors regarding reactor physics aspects;Carlsson;severe safety and economical issues,2006

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