질산용액에 UO<sub>2</sub> Pellet의 용해특성에 관한 연구

정원명; 박진호; 이규일; 유재형; 정경채

Journal of the Korean Industrial and Engineering Chemistry, Vol.9, No.3, 388-393, June, 1998

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질산용액에 UO₂ Pellet의 용해특성에 관한 연구

A Study on Dissolution Characteristics of UO₂ Pellet in Nitric Acid

정원명, 박진호, 이규일, 유재형, 정경채

초록

의료용 동위원소인 fission Mo(⁹⁹Mo)를 제조하기 위한 공정중 UO₂ 표적의 질산용해공정의 조업조건을 확립하기 위하여 UO₂ pellet의 유효표면적(s:0.034∼0.282cm²/g-UO₂), 질산농도(1.5∼10N), 반응온도 (40∼105℃)에 따른 UO₂ pellet의 용해특성을 확인하였다. 그 결과 용해속도가 UO₂ pellet의 유효표면적에 정비례하며 표면적이 클수록 그 경향이 뚜렸함을 확인하였고, 반응속도와의 관계가 dc/dt = 10.6s로 나타났다. 용해속도와 질산농도와의 관계는 일정온도(90℃)에서 [HNO₃]^1.42에 비례하는 것으로 나타났고, 온도변화에 따른 관계는 90℃까지는 온도가 증가함에 따라 용해속도가 급격히 증가하나 그 이상에서는 오히려 감소하는 것으로 나타났으며, 활성화 에너지가 36.3KJ/mol로 계산되었다.

The effects of surface area of UO₂ pellets(s:0.034∼0.282cm²/g-UO₂), concentration of nitric acid(1.5∼10N) and temperature(40∼105℃) on the dissolution rate were investigated in this experiment. The results showed that dissolution rate of UO₂ pellets was in direct proportion to effective surface area(s) and well fit to linear plot in high surface area. The dissolution rate was expressed as dc/dt = 10.6s at 90℃, [HNO₃]=8N, and proportioned to the power 1.42 of HNO₃ concentration. And also, the results showed that dissolution rate was sharply increased according to temperature increase in temperature below 90℃, but decreased in temperature above 90℃. Activation energy(E) was evaluated to be 36.3KJ/mol.

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[1] Sameh AA, Hans A, "Production Techniques of Fission Molibdenum-99," Radiochimia Acta 41, 65-72 (1987)

[2] IAEA, "Fission Molybdenum for MEdical Use," IAEA-TECDOC-515 (1989)

[3] 박진호, "Mo-99 제조기술 개발현황에 관한 연구," KAERI/AR-401/94 (1994)

[4] Charles DH, "Uranium Production Technology," 12-42 (1959)

[5] Blake CA, AECP-3212 (1951)

[6] Ahrland S, Acta. Chem. Scand., 8, 354 (1954)

[7] Shabbir M, Robins RG, J. Appl. Chem., 18 (1968)

[8] Shabbir M, Robins RG, J. Appl. Chem., 19 (1969)

[9] Inoue A, J. Nucl. Mater., 138 (1986)

[10] Ikeda K, J. Nucl. Sci. Technol., 32, 2 (1995)

[11] Ikeda K, J. Nucl. Mater., 224 (1995)

[12] Al Fredson PG, "Development of Processes for Pilot Plant Production of Purified Uranyl Nitrate Solution," AACE/E, 344 (1975)

[13] Wen CY, Ind. Eng. Chem., 60, 34 (1968)

[14] Taylor F, J. Appl. Chem., 13, 32 (1963)