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핵연료분말 제조공정에서 발생된 여액으로부터 우라늄 회수 및 회수된 우라늄 화합물의 열분해 특성
정경채,정지영,김병호,김태준,최종현,Jeong, Kyung-Chai,Jeong, Ji-Young,Kim, Byung-Ho,Kim, Tae-Joon,Choi, Jong-Hyeun 한국세라믹학회 2002 한국세라믹학회지 Vol.39 No.2
본 연구에서는 AUC 공정에서 발생되는 액체폐기물에 미량 함유되어 있는 우라늄을 회수/재사용하기 위해 액상에서 침전법을 이용하여 용해도가 작은 우라늄화합물을 얻었으며, 이 화합물에 대한 chemical analysis, thermal analysis, x-ray diffraction analysis 및 FT-IR 분석을 통해 물성 특성을 해석하였다. 연구결과, 화학분석 및 FT-IR 분석으로부터 우라늄화합물은 $UO_4{\cdot}2NH_4F$ 형태를 가지고 있음을 알 수 있었으며, 평균 2∼3${\mu}m$ 입자 크기를 갖는 hexagonal 형태를 나타내었다. 열 분해시 분해 온도에 따라 중간물질로 $UO_4F,\;UO_4,\;UO_3,\;U_3O_8$ 등으로 변환되었으며, 상온에서 800$^{\circ}C$까지의 공기분위기에서 일정한 가열속도로 열분해시킬 경우, $UO_4{\cdot}2NH_4F{\rightarrow}UO_4F{\rightarrow}UO_4{\rightarrow}UO_3{\rightarrow}U_3O_8$의 반응 메커니즘을 나타내었다. In this study, $UO_4{\cdot}2NH_4F$, the precipitates which has low solubility, was obtained by chemical precipitation method to recover and reuse the trace uranium from the liquid waste producing in AUC process and for this compound it was characterized by means of chemical analysis, TG-DTA, XRD and FT-IR analyses. This compound was analyzed as $UO_4{\cdot}2NH_4F$ and shape of this precipitate was hexagonal type, having the size of 2∼3 ${\mu}m$. Also, the intermediates were obtained as $UO_4F,\;UO_4,\;UO_3,\;and\;U_3O_8$ by the thermal decomposition over the temperature of 220, 310, 515 and 640$^{\circ}C$, respectively. It is concluded that under the condition of a constant heating rate of 5$^{\circ}C$/min in air atmosphere range of between room temperature and 800$^{\circ}C$, thermal decomposition reaction mechanism of $UO_4{\cdot}2NH_4F$ is as follow; $UO_4{\cdot}2NH_4F{\rightarrow}UO_4F{\rightarrow}UO_4{\rightarrow}UO_3{\rightarrow}U_3O_8$.
나트륨-물 반응에 의한 전열관 표면에서의 부식과 반응특성에 대한 연구
정경채 ( Kyung Chai Jeong ),정지영 ( Ji Yong Jeong ),김병호 ( Byung Ho Kim ),김태준 ( Tae Joon Kim ),최종현 ( Jong Hyeun Choi ),김의식 ( Eui Sik Kim ) 한국공업화학회 2003 공업화학 Vol.14 No.1
본 연구에서는 증기발생기 전열관 재질로 예상되는 페라이트 강을 사용해서, 액체 나트륨 분위기에서 미량 물누출 실험을 수행하여, 시편의 누출 부위와 표적표면에서 발생되는 재질의 부식현상. 나트륨-물 반응에 의한 온도 상승현상 등에 대한 특성을 관찰하였다. 실험결과, 시편의 누출구멍 주변은 나트륨부위에서 나트륨-물 반응에 의해 발생되는 부식 및 침식에 의한 wastage 현상에 의해 손상을 입어 누출 구멍의 직경이 확대되었으며, 누출 부위에서의 손상은 초기 누출구멍 크기인 150㎛에서 200㎛정도로 확대되었고, 표적표면에 나타난 손상부위의 크기는 약 1000㎛ 정도로 분석되었다. 또한, 표적표면에서의 온도는 나트륨-물 반응에 의해 형성되는 반응열에 의해 약 70-80℃ 정도 상승하였으며, 손상부위 표명을 EPMA 및 EDX로 분석한 결과, 나트륨 산화물과 전열관의 모지 금속을 구성하는 Fe이나 Cr 등의 원소와 반응하여 (NaOH+Na_2O)ㆍFe_xO_y나 (NaCrO_2+Na_2Cro_4) 같은 형태의 복합산화물을 형성하는 것으로 판명되었다. In this study we observed and analyzed the corrosion phenomena in a leak site and he effect of temperature at the target surface of heat transfer tube material by sodium-water reaction through water leakage in liquid sodium atmosphere. Surrounding of the leak hole of the specimen was damaged by the wastage phenomena due to corrosion and erosion of material, and the hole size, by damage of leak site, was extended from 150㎛to about 200㎛. Also, the damaged size appeared in the target surface was observed to be about 1000㎛ diameter. The temperature of target surface increased about 70~80℃ by the heat of sodium-water reaction even with a small leakage of 15mL water. From the results of EPMA and EDX analysis, damaged areas are found to be covered with complex compounds such as (NaOH+Na_2O)·Fe_xO_y or (NaCrO_2+Na_2CrO_4) mixed up with the sodium oxides by sodium-water reaction and the Fe or Cr element by matrix of tube material.
정지영,정경채,김병호,김태준,최종현,박남국 한국공업화학회 2002 응용화학 Vol.6 No.2
An experimental study for the investigation of the sodium-steam reaction phenomena was carried out. No significant aggressive explosion phenomena were observed as compared with that of sodium-water reactions. It was also observed that the rate of increase of reaction temperature decreases with increasing initial temperature of liquid sodium and that the temperature of the target depends upon the flow rate of injected steam.
액체소듐속에서 소듐-물반응에 의한 재질의 Wastage현상
정경채,정지영,김병호,김태준,최병해,최종현,김의식 한국공업화학회 2003 응용화학 Vol.7 No.1
In this study we observed and analyzed the corrosion phenomena in leak site and the effect on temperature at the target surface of heat transfer tube material by sodium-water reaction through water leakage in liquid sodium atmosphere. Surrounding of leak hole of the specimen was damaged by the wastage phenomena due to corrosion and erosion of material, and hole size by damage of leak site was extended from 150㎛ to about 200㎛. Also, the damaged size appeared in the target surface was observed to about 1000㎛ diameter. The temperature of target surface increased about 70~80℃ by the heat of sodium-water reaction even with the small leakage of 15㎖ water. From the results of EPMA and EDX analysis, damaged area are found to covered with complex compounds such as (NaOH+Na_2O) FexOy or (NaCrO_2+nA_2CrO4) mixed up with the sodium oxides by sodium-water reaction and the Fe or Cr element by matrix of tube sodium oxides by matrix of tube material.
정경채,정지영,김병호,김태준,최종현,김의식 한국공업화학회 2002 응용화학 Vol.6 No.2
In this study are observed and analyzed the corrosion phenomena in leak site and the effect on temperature at the target surface of heat transfer tube material by sodium-water reaction through small water leakage in liquid sodium atmosphere. Surrounding of leak hole of the specimen was damaged by the wastage phenomena due to corrosion and erosion of material, and the damage at the leak site was extended from 150㎛ to about 200㎛. Also, the size appeared in the target surface observed to about 1000㎛ diameter. The temperature of target surface increased about 70~80℃ by heat of sodium-water reaction in spite of the small leakage in 15㎖ of water. Also, from the results of EPMA and EDX analyses, damaged area are covered with complex compounds such as (NaOH+Na_2O) · Fe_xO_y or (NaCrO_2+Na_2CrO_4) which mixed up with the sodium oxides formed by sodium-water reaction and the Fe or Cr element composed of matrix in target material.
정경채,정지영,김병호,김태준,최종현 한국공업화학회 2002 응용화학 Vol.6 No.1
Design of the steam generator should be considered the safety about the sodium-water reaction occurred by water leakage in heat transfer tube. Water leakage mainly occurred from welding defect at the process of tube connection, the vibration of heat transfer tube bundle in steam generating system, fretting, and pin hole in original tube manufacturing. The classification of water leak divided to two parts, roughly, in case of the water leak studies. One is small leakage phenomena analysis, and the other is it of large leakage which was mainly treated to the evaluation on pressure increasing from hydrogen gas formed by sodium-water reaction in sodium system. In this study, the corrosion phenomena on the target tube surface appeared by small water leakage was analyzed, and the temperature increasing profile phenomena formed by sodium-water reaction through the leak nozzle under water medium was observed.