Numerical investigation of thermal gasification in enclosed screw-conveyor reactor for removal of 14C from irradiated graphite waste
Author:
Affiliation:
1. Department of Environmental Engineering, Kongju National University, Gongju, Republic of Korea
2. Department of Chemical Engineering, Kyonggi University, Suwon, Republic of Korea
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.1080/00223131.2020.1728413
Reference27 articles.
1. IAEA. Characterization, treatment and conditioning of radioactive graphite from decommissioning of nuclear reactors. Vienna: International Atomic Energy Agency (AU); 2006. (IAEA-TECDOC-1521).
2. Development of integrated waste management options for irradiated graphite
3. Behavior of Radioactive Elements during Thermal Treatment of Nuclear Graphite Waste Thermodynamic Model Analysis
4. Chemically reduced graphene contains inherent metallic impurities present in parent natural and synthetic graphite
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1. Single-Phase Flow Model of a Screw Reactor for Decontamination of Radioactive Graphite Waste Using Surface Gasification;Processes;2022-02-18
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