Creep properties of oxide and carbide fuels under irradiation-Reference-Cited by-同舟云学术

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Creep properties of oxide and carbide fuels under irradiation

Published:1977-03 Issue: Volume:65 Page:24-36
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Clough D.J.

Publisher

Elsevier BV

Subject

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

Reference14 articles.

1. Irradiation induced creep of ceramic fuels;Clough;AERE R6627,1970

2. Creep of fissile ceramic materials under neutron irradiation element;Brucklacher,1973

3. Observations on the low temperature creep properties of uranium carbide under irradiation;Clough;AERE R7772,1974

4. A model for in-reactor densification of UO2;MacEwen;Phil. Mag.,1975

Cited by 16 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. Compositionally complex carbide ceramics: A perspective on irradiation damage;Journal of Applied Physics;2024-05-22

2. On the creep mechanisms and macroscopic creep rate modeling of high-uranium-density composite fuels;Journal of Nuclear Materials;2023-12

3. Irradiation-Induced Creep and Re-Sintering of Large Grain Sized UO2 Fuel;Physics of Atomic Nuclei;2022-12

4. Modeling of Mesoscale Creep Behaviors and Macroscale Creep Responses of Composite Fuels Under Irradiation Conditions;Acta Mechanica Solida Sinica;2022-07-21

5. An improved model of fission gas atom transport in irradiated uranium dioxide;Journal of Nuclear Materials;2018-04

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