用于干式贮存铝壳乏核燃料的氢氧化铝薄膜的干燥和分析

IF 1.5 4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY
Robert J. Demuth, Anna L. D’Entremont, Rebecca Smith, Robert L. Sindelar, Travis W. Knight
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引用次数: 0

摘要

在铝包壳乏核燃料中,包壳表面的(氧)氢氧化物层承载着在反应堆和放电后暴露于水中时形成的化学吸附水。任何残留的水都会...
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Drying and Analysis of Aluminum (Oxy)hydroxide Films for Dry Storage of Aluminum-Clad Spent Nuclear Fuels
In aluminum-clad spent nuclear fuels, an (oxy)hydroxide layer on the surface of the cladding hosts chemisorbed water formed during reactor and post-discharge exposure to water. Any residual water i...
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来源期刊
Nuclear Technology
Nuclear Technology 工程技术-核科学技术
CiteScore
3.40
自引率
6.70%
发文量
116
审稿时长
4-8 weeks
期刊介绍: Nuclear Technology aims to be the leading international publication reporting new information in the practical applications of nuclear science and technology. We publish technical papers, technical notes, critical reviews, rapid communications, book reviews, and letters to the editor on all phases of applications of fundamental research to nuclear technology.
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