Nested loops explain low irradiation-induced swelling rate-Reference-Cited by-同舟云学术

Nested loops explain low irradiation-induced swelling rate

Published:2024-04 Issue: Volume:267 Page:119700
ISSN:1359-6454
Container-title:Acta Materialia
language:en
Short-container-title:Acta Materialia

Author:

Cui Lijuan,Du Yufeng,Yang Huilong,Schäublin Robin E.,Zongda Yang,Kano Sho,Hu Xunxiang,Abe Hiroaki

Funder

University of Tokyo

Ministry of Education, Culture, Sports, Science and Technology

Publisher

Elsevier BV

Reference74 articles.

1. Evolution of Cr /Cr 2 O 3 interface in Cr-coated zirconium alloy in high temperature steam;Wang;Corros. Sci.,2023

2. Materials Characterization TEM characterizations of a ZrO 2 /Cr composite coating on Zr-1Nb alloy after 1200 ◦ C steam oxidation;Xu;Mater. Charact.,2023

3. Improved irradiation resistance of Cr-Fe alloy for Cr-coated Zircaloy application in accident tolerant fuel;Cui;Scr. Mater.,2023

4. Experimental kinetic study of interdiffusion behavior and intermetallic compound Zr(Fe,Cr)2 formation at the Cr/Zry4 interface under elevated temperatures;Li;J. Nucl. Mater.,2023

5. Uncertainty analysis of ATF Cr-coated-Zircaloy on BWR in-vessel accident progression during a station blackout;Guo;Reliab. Eng. Syst. Saf.,2021

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1. Dislocation evolution and hardening of CoCrFeMnNi high entropy alloy under Fe ion irradiation at room temperature and 500 °C;Journal of Applied Physics;2024-09-04

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3. Workshop on development of accident tolerant fuel for light water reactor;Journal of the Atomic Energy Society of Japan;2024