High-temperature heating experiments on unirradiated ZrC-coated fuel particles
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference17 articles.
1. The effect of heat treatment on density and structure of SiC
2. Failure Mechanisms and Fission Product Release in High-Temperature Gas-Cooled Reactor Fuel under Conditions of Unrestricted Core Heatup Events
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1. Evaluation of diffusion behavior and mechanical characteristics in the ZrC-NbC pseudo-binary system;International Journal of Refractory Metals and Hard Materials;2024-06
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3. Effect of ZrB2 content on the densification, microstructure, and mechanical properties of ZrC-SiC ceramics;Journal of the European Ceramic Society;2020-02
4. Advanced Concepts in TRISO Fuel;Comprehensive Nuclear Materials;2020
5. Microstructure, properties and applications of Zr-carbide, Zr-nitride and Zr-carbonitride coatings: a review;Materials Advances;2020
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