Concentration profiles of neutron-induced radioactivities in UO2 fuel specimens
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference16 articles.
1. Fission-Product Behavior In Ceramic Oxide Fuel;Olander,1986
2. Release of Volatile Fission Products from UO2;Prussin,1984
3. Release of fission products (Xe, I, Te, Cs, Mo and Tc) from polycrystalline UO2
4. Spatial Distribution of U238Resonance Neutron Capture in Uranium Metal Rods
Cited by 5 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. Study of fission-product segregation in used CANDU fuel by X-ray photoelectron spectroscopy (XPS) II;Journal of Nuclear Materials;1994-03
2. Differences in Oxidation Behavior of Used CANDU Fuel During Prolonged Storage in Moisture-Saturated Air and Dry Air at 150°C;Nuclear Technology;1993-12
3. On the rim effect in high burnup UO2LWR fuels;Journal of Nuclear Materials;1992-07
4. Concerning the microstructure changes that occur at the surface of UO2 pellets on irradiation to high burnup;Journal of Nuclear Materials;1992-06
5. Concerning the microstructure changes that occur at the surface of UO2 pellets on irradiation to high burnup;Nuclear Materials for Fission Reactors;1992
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