In-situ TEM investigation of dislocation loop evolution in HR3 steel during Fe+ ion irradiation-Reference-Cited by-同舟云学术

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In-situ TEM investigation of dislocation loop evolution in HR3 steel during Fe+ ion irradiation

Published:2023-05 Issue: Volume:578 Page:154309
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Wang Jipeng,Guo Li,Luo Jinru,Song Jiangfeng,Shi Yan,Chen Chang'an

Funder

National Natural Science Foundation of China

Publisher

Elsevier BV

Subject

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

Reference55 articles.

1. Microstructural evolution of a silicon carbide-carbon coated nanostructured ferritic alloy composite during in-situ Kr ion irradiation at 300 °C and 450 °C;Bawane;J. Mater. Sci. Technol.,2021

2. A promising new class of irradiation tolerant materials: Ti2ZrHfV0.5Mo0.2 high-entropy alloy;Lu;J. Mater. Sci. Technol.,2019

3. Accident tolerant fuel cladding development: promise, status, and challenges;Terrani;J. Nucl. Mater.,2018

4. Corrosion resistance of candidate cladding materials for supercritical water reactor;Guo;Ann. Nucl. Energy,2019

5. Selection of fuel cladding material for nuclear fission reactors;Azevedo;Eng. Fail. Anal.,2011

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1. Identification of nano-sized precipitates in CLAM steel induced by 3.5 MeV Fe13+ ion irradiation;Journal of Nuclear Materials;2024-12

2. Effects of interstitial cluster mobility on dislocation loops evolution under irradiation of austenitic steel;Nuclear Science and Techniques;2024-07-21

3. Lattice Damage, Optical and Electrical Properties Induced by H and C Ions Implantation in Nd:YLF Crystals;Crystals;2024-01-31

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