Modeling the swelling performance of UMo alloys for Al-matrix dispersion fuel
Author:
Publisher
Elsevier BV
Subject
Materials Chemistry,Metals and Alloys,Mechanical Engineering,Mechanics of Materials
Reference28 articles.
1. Microstructural characteristics of DU–xMo alloys with x=7–12wt%
2. Development, preparation and characterization of uranium molybdenum alloys for dispersion fuel application
3. Crystal structure and magnetic behaviour of the ternary uranium and thorium-molybdenum chalcogenides UMo6S8, UMo6Se8 and ThMo6S8
4. Thermal compatibility studies of unirradiated UMo alloys dispersed in aluminum
5. Irradiation behavior of atomized U–10wt.% Mo alloy aluminum matrix dispersion fuel meat at low temperature
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1. Effects of Matrix Creep Properties on Effective Irradiation Swelling of U-10Mo/Zr Dispersion Nuclear Fuels;Frontiers in Energy Research;2022-03-17
2. Effects of UMo irradiation creep on the thermo-mechanical behavior in monolithic UMo/Al fuel plates;Journal of Nuclear Materials;2019-10
3. Molecular dynamics simulations of displacement cascade and threshold energy in ordered alloy Al3U;Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms;2019-06
4. A simple post modification method for novel porous superabsorbent p(acrylamide) hydrogels and their H2 production;Journal of Polymer Research;2014-11-26
5. Molecular Dynamics Simulation of Xe Behavior in U-Mo Alloys Fuel;Chinese Physics Letters;2014-04
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