Irradiation behavior of the interaction product of U-Mo fuel particle dispersion in an Al matrix-Reference-Cited by-同舟云学术

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Irradiation behavior of the interaction product of U-Mo fuel particle dispersion in an Al matrix

Published:2012-06 Issue:1-3 Volume:425 Page:181-187
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Kim Yeon Soo,Hofman G.L.

Publisher

Elsevier BV

Subject

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

Reference35 articles.

1. Y.S. Kim, G.L. Hofman, J. Rest, G. Shevlyakov, ANL-08/11, Argonne National Laboratory, 2008.

2. Low-temperature irradiation behavior of uranium–molybdenum alloy dispersion fuel

3. Y.S. Kim, G.L. Hofman, J. Nucl. Mater. (2011), accepted for publication.

4. Transmission electron microscopy investigation of irradiated U–7wt%Mo dispersion fuel

5. G.L. Hofman, M.R. Finlay, Y.S. Kim, H.J. Ryu, in: Proc. Internat. Mtg. Reduced Enrichment for Research and Test Reactors (RERTR), Boston, MA, USA, 2005. .

Cited by 26 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. Non-destructive analysis of swelling in the EMPIrE fuel test;Journal of Nuclear Materials;2022-06

2. Analytical local stress model for UMo/Al dispersion fuel;Journal of Nuclear Materials;2020-01

3. U-Mo Based Fuel System;Comprehensive Nuclear Materials;2020

4. Intermetallic Fuel Performance Modeling and Simulation;Comprehensive Nuclear Materials;2020

5. Quantitative comparability of heavy ion and in-pile irradiations on UMo fuel systems;Journal of Nuclear Materials;2018-08

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