在 Mo30W 基质中对 W 涂层 UN 内核进行热氢测试

IF 1.2 3区工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Science and Engineering Pub Date : 2024-04-15 DOI:10.1080/00295639.2024.2332001

Arne Cröll, Jamelle K. P. Williams, Brian Taylor, Martin P. Volz, Christopher McKinney, Timothy Coons, Jhonathan Rosales

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引用次数: 0

摘要

人们正在考虑将陶瓷单氮化铀（UN）作为核热推进反应堆燃料。为了避免或减少 UN 在所需的高温下发生解离，将其嵌入陶瓷材料中是一种有效的方法。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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Hot Hydrogen Testing of W-Coated UN Kernels in a Mo30W Matrix

Ceramic uranium mononitride (UN) is being considered as a reactor fuel for nuclear thermal propulsion. To avoid or reduce the dissociation of UN at the high temperatures needed, embedding it in a m...

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来源期刊

Nuclear Science and Engineering 工程技术-核科学技术

CiteScore

2.10

自引率

25.00%

发文量

审稿时长

3 months

期刊介绍： Nuclear Science and Engineering, the research journal of the American Nuclear Society, publishes articles on research and development related to peaceful utilization of nuclear energy, radiation, and alternative energy sources.