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방사성폐기물의 화학처리공정에 사용되는 유동관식 장치의 해석 : 물질전달 수율에 미치는 매개변수들의 민감도
유재형,이병직,심준보,김응호,Yoo, Jae-Hyung,Lee, Byung-Jik,Shim, Joon-Bo,Kim, Eung-Ho 한국방사성폐기물학회 2007 방사성폐기물학회지 Vol.5 No.1
It was intended in this study to investigate the effects of various parameters on the chemical reaction or mass transfer yield in a tubular-type nuclear waste treatment equipment. Since such equipments, as a tubular reactor, multistage solvent extractor, and adsorption column, accompany chemical reaction or mass transfer along the fluid-flowing direction, mathematical modeling for each equipment was carried out first. Then their behaviors of the chemical reaction or mass transfer were predicted through computer simulations. The inherent major parameters for each equipment were chosen and their sensitivities. affecting the reaction or mass transfer yield were analyzed. For the tubular reactor, the effects of axial diffusion coefficient and reaction rate constant on the reaction yield were investigated. As for the multistage solvent extractor, the backmixing of continuous phase and the distribution coefficient between fluid and solvent were considered as the major parameters affecting the extraction yield as well as concentration profiles throughout the axial direction of the extractor. For the adsorption column, the equilibrium constant between fluid and adsorbent surface, and the overall mass transfer coefficient between the two phases were taken as the major factors that affect the adsorption rate.
유재형,김정국,이한수,서인석,김은가,Yoo, Jae-Hyung,Kim, Jung-Kuk,Lee, Han-Soo,Seo, In-Seok,Kim, Eun-Ka 한국방사성폐기물학회 2011 방사성폐기물학회지 Vol.9 No.4
사용후핵연료의 파이로처리기술에 대한 국내외 특허동향을 분석하였다. 1975-2009년에 걸쳐 한국, 미국, 일본 및 유럽연합에서 출원된 특허에 대하여 출원국별, 출원인별, 연도별 및 세부기술분야별로 구분하여 그 내용을 비교함으로써 파이로처리기술 개발 현황을 분석하였다. 그리고 주요 출원인의 세부기술별 특허활동지수로부터 특정분야의 기술개발 편중도, 분석대상 특허의 피인용횟수와 패밀리수로부터 각국의 기술 경쟁력을 조사하였다. 또 장차 파이로처리기술의 실용화에 대비하여 필수 요소기술들을 도출하고 그에 대한 현기술 수준과 기술개발동향 등을 파악하였다. Analysis of foreign and domestic patents for pyroprocessing technology of spent nuclear fuels was carried out in this study. The current status of pyroprocessing technology development in such countries as Korea, USA, Japan and EU was analyzed by classifying the patents for 1975 through 2009 according to registration country, assignee, calendar year and technology area. The major assignees' activity indices were compared in order to find out whether there is any concentrated area of technical details. Technology competitiveness of the countries was also investigated from the information of patent citation number and family size. Furthermore, some essential unit technologies required for the commercialization of pyroprocessing were derived and examined in the aspect of the state of art as well as the trend of technology development.
고온전해분리 기술의 개요 및 기존 핵연료주기 대체 기술로서의 적합성 검토
유재형,이병직,이한수,김응호,Yoo, Jae-Hyung,Lee, Byung-Jik,Lee, Han-Soo,Kim, Eung-Ho 한국방사성폐기물학회 2007 방사성폐기물학회지 Vol.5 No.4
The technical feasibility of a pyroprocessing of PWR spent fuels to recover nuclear fuel materials, uranium and transuranic elements group(TRU), was examined in this study. Also its applicability as a new fuel cycle technology in terms of non-proliferation was investigated. First, various unit processes were combined to a pyroprocess. Then the flow aspects of such materials of issue as uranium, transuraniums, rare earth, noble metals and heat generating elements were examined on the flowsheet, which was obtained by the assumptions on the basis of various experimental results in this work or separation data collected from literatures. Consequently, the calculated results of the material balance for the whole process showed that uranium and TRU could be recovered as products by 98.0 % and 97.0 %, respectively, from a PWR spent fuel while removing the other elemental groups into radioactive wastes. On the one hand, the TRU product was found to emit a considerable amount of ${\gamma}$-ray as well as neutrons favorably contributing to the strategy of proliferation resistance.
회분식 제올라이트계에서 Cs 및 Sr 의 이온교환속도 연구
이일희,유재형,박현수 ( Eil Hee Lee,Jae Hyung Yoo,Hyun Soo Park ) 한국공업화학회 1993 공업화학 Vol.4 No.4
본 연구에서는 제올라이트에 의하여 Cs 및 Sr을 분리하는 무기이온 교환계에 있어서 물질전달 특성을 규명하는데 중점을 두었다. Cs이온의 경우 선택도가 우수한 AW300 및 AW500 제올라이트, Sr이온의 경우는 4A, 13X 제올라이트를 각각 선정하여 물질전달실험을 수행하였다. 실험조건으로는 25℃, 교반속도 300rpm, 재올라이트량 4g, Cs 및 Sr용액의 농도, 부피는 각각 1000ppm, 2000ppm의 0.5ℓ에서 회분식의 이온교환 방식을 채택하였다. 물질전달속도는 경막내 확산에 의해 지배됨을 알았으며, 경막 내 물질 전달계수는 10^(-4)∼10^(-3)㎝/sec, 입자내 겉보기 확산계수는 10^(-8)㎠/sec의 차수를 나타내었다. The characteristics of mass transfer in an inorganic ion exchange system where Cs and/or Sr are separated by means of zeolites was investigated. Experimental work to separate Cs or Sr was carried out for Cs-AW300 and CS-AW500 systems in case of Cs whereas for Sr-4A and Sr-l3X systems in case of Sr. The experimental conditions were chosen as follows in the batch type separation : temperature 25℃, agitation speed 300rpm, amount of zeolite 4g, volume of solution 0.5ℓ, and concentrations of solution 1000ppm, 2000ppm, respectively. As a result, it was found that the mass transfer rate is controlled mainly by the liquid film diffusion. The mass transfer coefficients in the film were found to be in the range of 10^(-4)∼10^(-3)㎝/sec, while the apparent diffusivity inside the particles was found to be in the order of 10^(-8)㎠/sec.
AUC ( Ammonium Uranyl Carbonate ) 의 열분해 및 환원 반응
김영환,유재형 ( Young Hwan Kim,Jae Hyung Yoo ) 한국공업화학회 1997 응용화학 Vol.1 No.1
Block copolymers with poly(tetrametnylene glycol)(PTMG) or poly(ethylene glycol)(PEG) spacers of different length and the 4,4`-(terephthaloyldioxy) dibenzoly unit have been synthesised by interfacial polymerizaiton. Thermal properties were found to be dependent on average length of hard segment as well as of the polyether segment. All copolyesters were elastomeric at room temperature. Thermtopic liquid crystalline behavior was found for all block copolyester and orginated from the hard segment.
Electrowinning에 의한 $LiF-BeF_2-ZrF_4$ 용융염에서 Zr 금속 분리
우문식,유재형,권수한,Woo, Mun-Sik,Yoo, Jae-Hyung,Kwon, Soo-Han 한국분석과학회 2000 분석과학 Vol.13 No.6
전해제련법을 이용하여 $LiF-BeF_2-ZrF_4$ (67-27-6 mol%) 용융염에서 Zr 금속 분리실험을 수행하였다. $LiF-BeF_2$ (72-28 mol%) 용융염과 $LiF-BeF_2-ZrF_4$ (67-27-6 mol%) 용융염의 분해 전압은 각각 -1.55, -1.35 volt로 측정되었고, Zr 분리실험 결과 인가전압 범위는 -1.4 -1.5 volt 사이가 적당하였다. 인가전류가 증가할수록 전착량은 증가하나 전류효율은 감소하였다. 그리고 반응온도가 증가할수록 $ZrF_4$의 기화로 인하여 전착량과 전류효율이 감소하였다. A study on the separation of Zr metal from $LiF-BeF_2-ZrF_4$ (67-27-6 mol%) molten salt was carried out using electrowinning. The decomposition potentials of the $LiF-BeF_2$ (72-28 mol%) and the $LiF-BeF_2-ZrF_4$ (67-27-6 mol%) molten salts were measured to be -1.55 and -1.35 volt, respectively. The Zr separation voltage from the salt were found to be in a range of -1.4 -1.5 volt. As increasing applied current, the deposition of molten salt on a cathode increases but the current efficiency decreases. In addition, the deposition and current efficiency decreases with increasing temperature.
$LiF-BeF_2-ZrO_2$ 용융염에서 증류수 침출에 의한 $ZrO_2$의 회수 - 증류수에서 $LiF-BeF_2-ZrF_4+ZrO_2$ 용융염의 용해현상 -
우문식,유재형,박현수,강영호,권수한,Woo, Mun-Sik,Yoo, Jae-Hyung,Park, Hyun-Soo,Kang, Young-Ho,Kwon, Soo-Han 한국분석과학회 2000 분석과학 Vol.13 No.6
$LiF-BeF_2-ZrF_4$(63-30-7 mol%) 용융염은 상온에서 증류수 1ml당 최고 0.02g까지 용해율 99.9%로 용해되었다. 그리고 $ZrF_4$를 열가수분해시켜 제조된 $ZrO_2$ 산화물을 포함하는 $LiF-BeF_2-ZrF_4$ 용융염에서 $ZrO_2$ 산화물을 증류수로 침출시켜 회수하였다. 회수된 $ZrO_2$ 산화물의 결정모양은 손상되지 않았다. $LiF-BeF_2-ZrF_4$(63-30-7 mol%) molten salt was dissolved up to 0.02g in 1ml of distilled water at room temperature. $ZrO_2$ oxide made from $ZrF_4$ through pyrohydrolysis was recovered by leaching in distilled water with $LiF-BeF_2-ZrF_4$molten salt including it at room temperature. The crystalline sharpness of recovered $ZrO_2$ oxide was not damaged.