Developmental Study of Dry Decontamination for Tritiated Wastes
Author:
Affiliation:
1. KAKEN Co.Ltd, Horimachi 1044 Mito, Ibaraki 310-0903, Japan +81-29-227-4485
2. Hydrogen Isotope research Center Toyama Univ., Gofuku 3190 Toyama 930-8555, Japan +81-76-445-6925
Publisher
Informa UK Limited
Subject
Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Civil and Structural Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/FST02-A22685
Reference5 articles.
1. Decontamination and Decommissioning of Nuclear Facilities
2. Surface analysis of carbon on ozone treated metals
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1. Experimental Trials of Methods for Metal Detritiation for JET;Fusion Science and Technology;2007-07
2. Detritiation of type 316 stainless steel by treatment with liquids at ambient temperature;Journal of Nuclear Materials;2006-07
3. Chronic Release of Tritium from SS316 at Ambient Temperature: Correlation Between Depth Profile and Tritium Liberation;Fusion Science and Technology;2005-07
4. Tritium uptake by SS316 and its decontamination;Journal of Nuclear Materials;2004-08
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