Fission gas diffusion and release for Cr2O3-doped UO2: From the atomic to the engineering scale-Reference-Cited by-同舟云学术

Fission gas diffusion and release for Cr2O3-doped UO2: From the atomic to the engineering scale

Published:2021-03 Issue: Volume:545 Page:152590
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Cooper Michael WD,Pastore Giovanni,Che Yifeng,Matthews Christopher,Forslund Axel,Stanek Christopher R,Shirvan Koroush^ORCID,Tverberg Terje,Gamble Kyle A,Mays Brian,Andersson David A

Funder

U.S. Department of Energy

Publisher

Elsevier BV

Subject

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

Reference71 articles.

1. Thermophysical properties database of materials for light water reactors and heavy water reactors;Agency,2006

2. Thermophysical properties of U3Si2 to 1773 K;White;J. Nucl. Mater.,2015

3. Advanced doped UO2 pellets in LWR applications;Arborelius;J. Nucl. Sci. Technol.,2006

4. Fission gas release and swelling in UO2 doped with Cr2O3;Killeen;J. Nucl. Mater.,1980

5. Factors governing microstructure development of Cr2O3-doped UO2 during sintering;Bourgeois;J. Nucl. Mater.,2001

Cited by 39 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. Consideration of Cr-doped UO2 fuel performance for a Fluoride-Cooled High Temperature Reactor concept;Annals of Nuclear Energy;2024-12

2. Chromia-doped UO2 fuel: An engineering model for chromium solubility and fission gas diffusivity;Journal of Nuclear Materials;2024-12

3. Modeling and design of a separate effects irradiation test targeting fission gas release from Cr-doped UO2;Nuclear Engineering and Design;2024-12

4. Transient behavior of oxide fuels with controlled microstructure and Cr2O3 additive;npj Materials Degradation;2024-07-16

5. Machine learning method to determine concentrations of structural defects in irradiated materials;Computational Materials Science;2024-06