Evolution under Irradiation of Optimized Austenitic Steel For Gen-IV Reactors. Impact on Fuel Cladding Properties and Performances-Reference-Cited by-同舟云学术

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Evolution under Irradiation of Optimized Austenitic Steel For Gen-IV Reactors. Impact on Fuel Cladding Properties and Performances

Published:2016 Issue: Volume:115 Page:04003
ISSN:2100-014X
Container-title:EPJ Web of Conferences
language:
Short-container-title:EPJ Web of Conferences

Author:

Courcelle Arnaud,Bisor Caroline,Piozin Emma,Kountchou Mikael,Gavoille Pierre,Le Flem Marion,Séran Jean-Louis

Publisher

EDP Sciences

Link

http://epjwoc.epj.org/10.1051/epjconf/201611504003/pdf

Cited by 10 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. High temperature tensile and creep properties of the new cladding steel of 15-15Ti-Y;Nuclear Materials and Energy;2024-06

2. Cavity Swelling of 15-15Ti Steel at High Doses by Ion Irradiation;Materials;2024-02-17

3. The influence of Y addition on oxide layers of 15-15Ti-Y steel exposed to static Pb-Bi alloys with containing oxygen;Journal of Nuclear Materials;2024-01

4. Microstructure and mechanical properties of the new cladding austenitic stainless steel of 15–15Ti–Y after aging at 500–700 °C for up to 1000 h;Materials Science and Engineering: A;2023-03

5. A peridynamic elasto-plastic damage model for ion-irradiated materials;International Journal of Mechanical Sciences;2023-01

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