In-situ TEM study of loop evolution in FeCrAl alloy under Fe+ irradiation: Effects of temperatures, dislocations and precipitates-Reference-Cited by-同舟云学术

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In-situ TEM study of loop evolution in FeCrAl alloy under Fe+ irradiation: Effects of temperatures, dislocations and precipitates

Published:2022-03 Issue:1 Volume:1 Page:100001
ISSN:2773-1839
Container-title:Nuclear Analysis
language:en
Short-container-title:Nuclear Analysis

Author:

Pei Kefei,Ran Guang,Li Yipeng,Cao Ziqi,Cui Dewang,Zhang Ruiqian,Yang Gang

Funder

National Natural Science Foundation of China

Xiamen University

Publisher

Elsevier BV

Reference57 articles.

1. Advanced oxidation-resistant iron-based alloys for LWR fuel cladding;Terrani;J. Nucl. Mater.,2014

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

3. Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors;Yamamoto;J. Nucl. Mater.,2015

4. Irradiation-enhanced a' precipitation in model FeCrAl alloys;Edmondson;Scripta Mater.,2016

5. Effects of Laves phase particles on recovery and recrystallization behaviors of Nb-containing FeCrAl alloys;Sun;Acta Mater.,2018

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. Dislocation loops and hardening induced by Au ion irradiation in FeCrAl alloys with three solute concentrations;Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms;2024-02

2. Effect of He-ions irradiation on the microstructure and mechanical properties of TiTaNbZr refractory medium-entropy alloy film;Vacuum;2023-11

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