Oxygen potential of (U0.88Pu0.12)O2±x and (U0.7Pu0.3)O2±x at high temperatures of 1673–1873K
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference23 articles.
1. A study of the ternary system U02-Pu02-Pu203
2. The uranium-plutonium-oxygen ternary phase diagram
3. Lattice parameters of (U, Pu, Am, Np)O2−x
4. Thermal conductivities of hypostoichiometric (U, Pu, Am)O2−x oxide
5. Effect of Oxygen-to-Metal Ratio on Melting Temperature of Uranium and Plutonium Mixed Oxide Fuel for Fast Reactor
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1. Oxygen potential measurement of U0.85Am0.15O2 at 1473, 1573, and 1673 K;Journal of Nuclear Materials;2024-10
2. Uranium–plutonium–americium cation interdiffusion in polycrystalline (U,Pu,Am)O2±x mixed oxides;Journal of Nuclear Materials;2024-01
3. A science‐based mixed oxide property model for developing advanced oxide nuclear fuels;Journal of the American Ceramic Society;2023-12-17
4. Monitoring and simulation of the fuel irradiation behavior in nuclear reactors based on phononic crystal structure;Scientific Reports;2023-07-29
5. Oxygen potential of neodymium-doped U0.817Pu0.180Am0.003O2± uranium–plutonium–americium mixed oxides at 1573, 1773, and 1873K;Journal of Nuclear Materials;2023-07
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