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Removal of Uranium by an Alkalization and an Acidification from the Thermal Decomposed Solid Waste of Uranium-bearing Sludge KCI 등재 SCOPUS

알카리화 및 산성화에 의한 우라늄 함유 슬러지의 열분해 고체 폐기물로부터 우라늄 제거

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방사성폐기물학회지 (Journal of the Korean Radioactive Waste Society)
한국방사성폐기물학회 (Korean Radioactive Waste Society)
초록

본 연구는 우라늄 변환시설 운전 중에 발생된 우라늄 함유 슬러지를 가열 처리하여 분말 형태로 저장 중인 우 라늄 함유 슬러지의 열분해 고체폐기물 (Thermal Decomposed Solid Waste of uranium-bearing sludge : TDSW)을 대상으로 TDSW의 용해, TDSW 질산 용해액의 알카리화에 의한 불순물 제거 및 탄산염 알카리화 용 액의 산성화에 의한 U 선택적 제거/회수 특성 등을 규명하였다. TDSW의 용해는 질산용해가 탄산염 산화용해 보다 효과적이었다. 1M 질산에서 TDSW의 약 30wt%가 고체 잔류물로 불용해되었고, TDSW 내 함유 U은 99% 이상이 용해되었다. TDSW의 질산 용해액의 알카리화는 탄산염에 의한 알카리화가 불순물 제거 측면에서 보 다 효과적이며, 탄산염 알카리화 (pH 약 9)에서 U과 공용해된 Ca, Al, Zn 및 Fe 등의 98±1%가 제거되었다. 그 리고 불순물이 거의 제거된 알카리화 용액 (0.5 M H2O2 첨가)의 산성화 (pH 약 3) 에서 U의 99% 이상을 회수 할 수 있어 TDSW로부터 U을 선택적으로 제거/회수할 수 있었다.

This study has been carried out to elucidate the characteristics of the dissolution for Thermal Decomposed Solid Waste of uranium-bearing sludge (TDSW), the removal of impurities by an alkalization in a nitric acid dissolving solution of TDSW, and the selective removal (/recovery) of uranium by an acidification in an carbonate alkali solution, respectively. TDSW generated by thermal decomposition of U-bearing sludge which was produced in the uranium conversion plant operation, was stored in KAERI as a solid- powder type. It is found that the dissolution of TDSW is more effective in nitric acid dissolution than oxidative-dissolution with carbonate. At 1 M nitric acid solution, TDSW was undissolved about 30wt% as a solid residue, and uranium contained in TDSW was dissolved more than 99%. In order to the alkalization for the nitric acid dissolving solution of TDSW, carbonate alkalization is more effective with respect to remove the impurities. At the carbonate alkali solution controlled to about 9 of pH, Al, Ca, Fe and Zn co- dissolved with U in dissolution step was removed about 98±1%. On the other hand, U could be recovered more than 99% by an acidification at pH about 3 in a carbonate alkali solution, which was nearly removed the impurities, adding 0.5M H2O2. It was found that uranium could be selectively recovered (/removed) from TDSW.

목차
Abstract   요약   1. 서론   2. 실험    2.1 우라늄 함유 열분해 고체폐기물 (TDSW)    2.2 실험 방법    2.3 분석   3. 결과 및 토의    3.1 TDSW의 용해    3.2 TDSW 질산 용해액의 알카리화 (alkalization)    3.3 우라늄의 산성화 침전 (acidification)   4. 결론   REFERENCES
저자
  • Eil-Hee Lee(Korea Atomic Energy Research Institute) | 이일희 Corresponding Author
  • Han-Beom Yang(Korea Atomic Energy Research Institute) | 양한범
  • Keun-Young Lee(Korea Atomic Energy Research Institute) | 이근영
  • Kwang-Wook Kim(Korea Atomic Energy Research Institute) | 김광욱
  • Dong-Yong Chung(Korea Atomic Energy Research Institute) | 정동용
  • Jei-Kwon Moon(Korea Atomic Energy Research Institute) | 문제권