Behavior of Radioactive Elements during Thermal Treatment of Nuclear Graphite Waste : Thermodynamic Model Analysis

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概要

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• Nuclear graphite waste retains various radioactive elements. This study investigated the behavior of the radioactive elements during a thermal treatment of the nuclear graphite waste, based on the thermodynamic equilibrium. Two typical thermal conditions were simulated: an excess air incineration and a hydrothermal oxidation. Tritium, 14C and 36Cl are expected to be present in the gas phase throughout the whole waste thermal systems. 133Ba, 90Sr, 22Na, and 137Cs were analyzed to be semi-volatile elements. Their behavior will be dependent upon the gaseous atmosphere as well as the operating temperature. Uranium species are expected to convert into a gas-phase UO3 at temperatures above 1,000°C under excess air incineration atmospheres. Other radioactive elements such as 59Ni, 60Co, 141Ce, 152Eu and 241Am are non-volatile at temperatures up to 1,200°C, regardless of the gaseous atmosphere being simulated.

• 社団法人 日本原子力学会の論文
• 2005-10-25

著者

• Lee Kune-woo

  Nuclear Fuel Cycle R&d Group Korea Atomic Energy Res. Inst.

• EUN Hee-Chul

  Quantum Energy Chemical Engineering, University of Science and Technology

• YANG Hee-Chul

  Nuclear Fuel Cycle R&D Group, Korea Atomic Energy Research Institute

• LEE Dong-Gyu

  Nuclear Fuel Cycle R&D Group, Korea Atomic Energy Research Institute

• OH Won-Zin

  Nuclear Fuel Cycle R&D Group, Korea Atomic Energy Research Institute

• Oh Won-zin

  Nuclear Fuel Cycle R&d Group Korea Atomic Energy Research Institute

• Eun Hee-chul

  Quantum Energy Chemical Engineering University Of Science And Technology

• Yang Hee-chul

  Nuclear Fuel Cycle R&d Group Korea Atomic Energy Research Institute

関連論文

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• Characteristics of Oxidation Reaction of Rare-earth Chlorides for Precipitation in LiCl-KCl Molten Salt by Oxygen Sparging
• Molten Salt Oxidation of Ion-exchange Resins Doped with Toxic Metals and Radioactive Metal Surrogates
• Analysis of Combustion Kinetics of Powdered Nuclear Graphite by using a Non-isothermal Thermogravimetric Method
• Behavior of Radioactive Elements during Thermal Treatment of Nuclear Graphite Waste : Thermodynamic Model Analysis

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