Properties of zirconium carbide for nuclear fuel applications

Author:

Katoh Yutai,Vasudevamurthy Gokul,Nozawa Takashi,Snead Lance L.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Cited by 218 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献

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. Mechanical and thermal properties of densified ZrC (x = 0.5, 0.7 and 1.0) ceramics;Journal of the European Ceramic Society;2024-04

3. Synthesis of porous ZrC particles derived from MOF-801;International Journal of Refractory Metals and Hard Materials;2024-04

4. Swift heavy ion irradiation effects in zirconium and hafnium carbides;Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms;2024-03

5. On the oxidation and ignition of uranium carbide fragments in air and comparison with zirconium carbide oxidation;Journal of Nuclear Materials;2024-02

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