Thermochemical assessment of oxygen gettering by SiC or ZrC in PuO2−x TRISO fuel
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference25 articles.
1. Deep-Burn: making nuclear waste transmutation practical
2. A Hybrid Transport-Diffusion Algorithm for Monte Carlo Radiation-Transport Simulations on Adaptive-Refinement Meshes inXYGeometry
3. Kernel Migration for HTGR Fuels from the System Th-U-Pu-C-O-N
4. Carbon Thermal Diffusion in the UC2-C System
5. Performance analysis of TRISO coated fuel particles with kernel migration
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1. Ar-ion- and electron-irradiated ZrC layers in ZrC-SiC-coated surrogate TRISO fuel particles;Journal of the European Ceramic Society;2024-05
2. Irradiation Performance: High-Temperature Gas Reactor Fuels;Encyclopedia of Nuclear Energy;2021
3. Role of microstructure on CO corrosion of SiC layer in UO2-TRISO fuel;Journal of Nuclear Materials;2020-08
4. Advanced Concepts in TRISO Fuel;Comprehensive Nuclear Materials;2020
5. A Neutronic Investigation of the Use of Fully Ceramic Microencapsulated Fuel for Pu/Np Burning in PWRs;Nuclear Technology;2014-04
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