Behavior of FeCrAl-ODS cladding tube under loss-of-coolant accident conditions-Reference-Cited by-同舟云学术

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Behavior of FeCrAl-ODS cladding tube under loss-of-coolant accident conditions

Published:2023-08 Issue: Volume:582 Page:154467
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Narukawa Takafumi^ORCID,Kondo Keietsu^ORCID,Fujimura Yuki,Kakiuchi Kazuo,Udagawa Yutaka^ORCID,Nemoto Yoshiyuki^ORCID

Publisher

Elsevier BV

Subject

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

Reference39 articles.

1. Event sequence of the Fukushima Daiichi accident;Mizokami,2015

2. Accident tolerant fuels for LWRs: a perspective;Zinkle;J. Nucl. Mater.,2014

3. Overview of accident-tolerant fuel R&D program in Japan;Yamashita,2019

4. Development of accident tolerant FeCrAl-ODS fuel cladding for BWRs in Japan;Sakamoto;J. Nucl. Mater.,2021

5. Fuel behavior under loss-of-coolant accident situations;Chung;Nucl. Eng. Technol.,2005

Cited by 3 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. Oxidation and embrittlement behavior of FeCrAl-ODS cladding tube under loss-of-coolant accident conditions;Journal of Nuclear Materials;2023-12

2. Microstructure dependent burst behavior of oxide dispersion–strengthened FeCrAl cladding;Materials & Design;2023-10

3. Research progress in high-temperature thermo-mechanical behavior for modelling FeCrAl cladding under loss-of-coolant accident condition;Progress in Nuclear Energy;2023-10

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