Study on Preparation Process and Performance of Tungsten-based Uranium Nitride Microspheres Dispersed Fuel

CERMET dispersion fuel is currently a hotspot in the research and development of fuels for nuclear thermal propulsion (NTP) reactors. Uranium nitride (UN) has a uranium density 40% greater than that of uranium dioxide (UO2), as well as the advantages of high thermal conductivity and good resistance...

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Bibliographic Details
Main Author: LIU Wentao1, 2,  DU Jiangping1, 2,  ZHAO Yumeng1, 2,  MA Chunyu2,  LIU Wei1, 2,  CAI Zhenfang2
Format: Article
Language:English
Published: Editorial Board of Atomic Energy Science and Technology 2024-07-01
Series:Yuanzineng kexue jishu
Subjects:
Online Access:https://yznkxjs.xml-journal.net/article/doi/10.7538/yzk.2024.youxian.0174