Journal of the Korean Industrial and Engineering Chemistry, Vol.8, No.3, 430-437, June, 1997
핵연료분말 제조공정 여액으로부터 Uranyl-peroxide 화합물의 제조
Uranyl Peroxide Compound Preparation from the Filtrate for Nuclear Fuel Powder Production Process
초록
핵연료 분말제조 공정에서 발생하는 여액중의 미량 우라늄과 과산화수소 용액을 반응시켜 uranyl-peroxide 화합물을 제조하였다. 여액에 CO32-가 공존할 경우에는 용해되어 있는 UO22+가 침전되지 않기 때문에, 여액을 98℃로 가열하여 CO32-를 우선 제거하였다. Uranyl-peroxide 화합물 제조시 최적조건으로는 암모니아 가스로 여액의 pH를 9.5로 조절한 후 과량의 과산화수소 용액을 10ml/lit.-filtrate로 첨가하여 1시간 ageing시킬 때이며, 처리후 여액중의 우라늄농도는 3ppm 이하로 나타났다. 제조된 uranyl-peroxide 화합물을 FT-IR, X-ray, TG 및 화학분석 등을 통해 분석한 결과 화합물의 조성은 UO4·2NH4F로 나타났으며, 초기 생성된 1∼2㎛의 UO4·2NH4F 입자들은 반응온도 60℃ 및 pH 9.5에서 약 4㎛로 성장하였다. 최적조건에서 제조된 입자들의 고/액 분리효율은 pH의 증가 및 반응온도의 상승에 따라 증가하는 경향으로 나타났다. 한편, 제조된 입자들의 결정형태는 SEM 및 XRD에 의한 분석결과 octahedral 형태로 나타났으며, 이 분말을 공기분위기에서 650℃까지 열분해한 결과 U3O8으로 판명되어 핵연료 분말제조 공정으로 재순환이 가능하였다.
Uranyl-peroxide compound was prepared by the reaction of excess hydrogen peroxide solution and trace uranium in filtrate from nuclear fuel conversion plant. The CO32- in filtrate was removed first by heating more than 98℃, because uranyl-peroxide compound could not be precipitated by CO32- remaining in filtrate. The optimum condition for uranyl-peroxide compound was ageing for 1 hr after controling the pH with NH3 gas and adding the excess H2O2 of 10ml/lit.-filtrate. Uranium concentration in the filtrate was appeared to 3 ppm after the precipitation of uranyl-peroxide compound, and the chemical composition of this compound was analyzed to UO4·2NH4F with FT-IR, X-ray diffractometry, TG and chemical analysis. Also, this fine particle, about 1∼2㎛, could be grown up to 4 ㎛ at pH 9.5 and 60℃. The separation efficiency of precipitate from mother liquor was increased with increase of pH and reaction temperature. Otherwise, the crystal form of this particle showed octahedral by SEM and XRD, and U3O8 powder was obtained by thermal decomposition at 650℃ in air atmosphere.
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