Thermal conductivity of SIMFUEL
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference28 articles.
1. Thermal Conductivity and Thermal Radiation Properties of UO 2
2. Thermal conductivity of solid UO2: Critique and recommendation
3. A recommendation for the thermal conductivity of UO2
4. A re-appraisal of the thermal conductivity of UO2 and mixed (U, Pu) oxide fuels
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1. The Effects of Irradiation on Structure and Leaching of Pure and Doped Thin-Film Ceria SIMFUEL Models Prepared via Polymer-Templated Deposition;Journal of Nuclear Engineering;2024-05-08
2. Experimental techniques for investigating thermal transport in nuclear materials;Journal of Nuclear Science and Technology;2024-03-28
3. Modeling of OECD/NEA P2M Benchmark Cases by Means of TRANSURANUS Code;Nuclear Technology;2023-08-21
4. New recommendation for the thermal conductivity of irradiated (U, Pu)O2 fuels under fast reactor conditions. Comparison with recent experimental data;Journal of Nuclear Materials;2023-04
5. Thermal Energy Transport in Oxide Nuclear Fuel;Chemical Reviews;2021-12-17
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