Kr ion irradiation study of the depleted-uranium alloys-Reference-Cited by-同舟云学术

Kr ion irradiation study of the depleted-uranium alloys

Published:2010-12 Issue:1 Volume:407 Page:48-54
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Gan J.,Keiser D.D.,Miller B.D.,Kirk M.A.,Rest J.,Allen T.R.,Wachs D.M.

Publisher

Elsevier BV

Subject

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

Reference18 articles.

1. Microstructure of U3Si2 fuel plates submitted to a high heat flux

2. Post-irradiation examination of uranium–7wt% molybdenum atomized dispersion fuel

3. Y.S. Kim, G. L. Hofman, H. J. Ryu, J. Rest, Thermodynamic and metallurgical considerations to stabilizing the interaction layers of U–Mo/Al dispersion fuel, in: Proceedings of the International Meeting on RERTR, Boston, USA, November 6–10, 2005.

4. Saturation behavior of cascade damage production using fission fragment and ion irradiations

5. A simulation of the swelling of intermetallic reactor fuels

Cited by 10 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. Irradiation induced structural change in Mo2Zr intermetallic phase;Scripta Materialia;2016-08

2. In situ TEM and synchrotron characterization of U–10Mo thin specimen annealed at the fast reactor temperature regime;Materials Characterization;2015-12

3. Microstructural Characterization of the U-9.1Mo Fuel/AA6061 Cladding Interface in Friction-Bonded Monolithic Fuel Plates Irradiated in the RERTR-6 Experiment;Metallurgical and Materials Transactions E;2015-09

4. Phase development in a U–7wt.% Mo vs. Al–7wt.% Ge diffusion couple;Journal of Nuclear Materials;2013-10

5. Effects of irradiation on the microstructure of U–7Mo dispersion fuel with Al–2Si matrix;Journal of Nuclear Materials;2012-06