Detritiation of type 316 stainless steel by treatment with liquids at ambient temperature
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference25 articles.
1. Assessment and selection of materials for ITER in-vessel components
2. Screen Test of Tritium Recovery from Stainless Steel Type 316
3. Effect of Water Vapor on Tritium Decontamination of Stainless Steel 316
4. Developmental Study of Dry Decontamination for Tritiated Wastes
5. Oxidative Decontamination of Tritiated Materials Employing Ozone Gas
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1. Distribution of Tritium in the Near Surface of Candidate Structural Materials for Fusion Reactors. Type 304L Stainless Steel, Inconel, Hastelloy, Eurofer-97, Oxide Dispersion-Strengthened Alloy 14YWT;IEEE Transactions on Plasma Science;2024
2. Influence of Microstructure on the Absorption of Tritium into Gold-Plated 316 Stainless Steel;Fusion Science and Technology;2023-01-27
3. Detritiation of the Electrostatic Spectrometer of Troitsk Nu-mass Experiment;Fusion Science and Technology;2021-12-06
4. Tritium retention in displacement-damaged tungsten exposed to deuterium-tritium gas mixture at elevated temperatures;Fusion Engineering and Design;2021-01
5. Distribution of Tritium in the Near Surface of Type 316 Stainless Steel;Fusion Science and Technology;2019-09-05
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