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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2004.1
- 수록면
- 808 - 815 (8page)
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이 논문의 연구 히스토리 (3)
2005
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This study investigated the thermal behavior of the nuclear graphite waste generated from the decommissioning of the Korean nuclear research reactor. The first part study investigated the decomposition rate of the nuclear graphite waste up to 1000°C under various oxygen partial pressures using a thermo-gravimetric analyzer (TGA). Tested graphite waste sample is not easily destroyed in the oxygen-deficient condition. However, the gas-solid oxidation reaction was found to be very effective in the presence of oxygen. No significant amount of the products of incomplete combustion was formed even in the limited oxygen concentration of 4% O2. The influence of temperature and oxygen partial pressure was evaluated by the kinetic analysis of the thermo-gravimetric data. The activation energy and the reaction order of graphite oxidation were evaluated as 128kJ/mole and 1.1, respectively. The second part of this study investigated the behavior of radioactive elements under graphite oxidation atmosphere using thermodynamic equilibrium model. 22Na, 134Cs and 137Cs were found be the semi-volatile elements. Since volatile uranium species can be formulated at high temperatures above 1050°C, the temperature of incinerator furnace should be minimized. Other corrosion/activation products, fission products and transuranic elements were found to be the non-volatile species.
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