다공성 고분자촉매 담체의 제조 특성

강희석,이한수,정흥석,안도희,손순환,정양근,송명재 ( Hee Suk Kang,Han Soo Lee,Hongsuk Chung,Do Hee Ahn,Soon Hwan Son,Yang Geun Chung,Myung Jae Song ) 한국공업화학회 1996 공업화학 Vol.7 No.4

중수형 발전소에서 삼중수소 제거 공정에 이용되는 소수성 고분자촉매의 담체인 스티렌-디비닐벤젠 공중합체의 제조 특성을 실험하였다. 스티렌-디비닐벤젠 고분자담체의 제조시 담체의 표면 특성에 대한 용매의 영향을 고찰하기 위하여 일정한 용매계에서 용매비를 변화시켜 solvating power 값을 구하였다. 거시기공 형태의 담체가 제조되기 위한 solvating power는 가교도가 20%일 때 3 이상, 가교도가 40%일 때는 1 이상의 값이 필요하였으며 약 40℃에서 2시간 이상 용액의 안정이 필요하였다. 또한 후처리 방법은 담체를 건조시키기 전에 용매를 제거하는 방법이 가장 우수한 기공 특성을 나타내었다. 담체의 입자 크기는 교반속도 및 계면활성제의 농도가 낮을수록 더 크게 생성됨을 알 수 있었다. This study represents the synthetic characteristics of styrene-DVB copolymer which is used as a catalyst support for the removal of tritium in CANDU. To evaluate the effect of solvent on the styrene-DVB polymeric support, the solvating power dependent on various kinds and composition of solvents was calculated. In order to synthesize the macroreticular type polymer bead, the following conditions are needed; solvating power should be higher than 1 for 20% of crosslinkage and higher than 3 for 40% of crosslinkage. Stabilization of organic monomers at about 40℃ for more than 2 hours is prerequisite. Removal of solvent prior to drying is preferred for the post-treatment of the bead. The polymer particle size was increased by lowering concentration of surfactant and stirring speed.

방사성 폐기물 소각공정을 위한 선택적 촉매 환원법 연구

이한수,김인태,정흥석,안도희,김종호,양희성,황재영,김상환 ( Han Soo Lee,In Tae Kim,Hongsuk Chung,Do Hee Ahn,Jong Ho Kim,Hee Sung Yang,Jae Young Hwang,Sang Hwan Kim ) 한국공업화학회 1996 공업화학 Vol.7 No.4

방사성 폐기물 소각로의 배기가스 중에 포함되어 있는 NO_x를 제거하기 위하여 선택적 촉매 환원법에 활용되는 촉매들의 특성을 조사하였다. 촉매는 V₂O_5, MoO₃, 그리고 SnO₂를 하니컴 형태의 TiO₂담체에 담지시켜 제조하였으며 촉매의 종류, 반응온도, feed의 조성, NH₃/NO 몰비의 영향 등이 반응특성에 미치는 영향을 실험실 규모의 반응기에서 조사하였다. 10% V₂O_5/TiO₂촉매가 350℃에서 94.4%의 높은 NO→N₂전환율을 보였으며 열적 안정성이 좋은 MoO₃의 첨가는 높은 전환율을 보이는 온도범위를 확장시켜 주었다. The characterization of catalysts for the selective catalytic reduction(SCR) was investigated to remove NO_x discharge from radioactive waste incinerator. The catalyst was prepared by impregnating V₂O_5, MoO₃, and SnO₂on honeycomb shaped TiO₂. The effects of the type of catalysts, reaction temperature, feed composition, and mole ratio of NH₃/NO on the reaction characteristics were evaluated in a laboratory scale reactor. The 10% V₂O_5/TiO₂ catalyst showed the highest NO to N₂conversion of 94.4% at 350℃ and the temperature range for higher conversion was broadened by adding thermally stable promoters, MoO₃.

실리카라이트에 담지된 백금촉매의 수소흡착특성 연구

안도희,백승우,이한수,정흥석 ( Do Hee Ahn,Seung Woo Park,Han Soo Lee,Hongsuk Chung ) 한국공업화학회 1996 공업화학 Vol.7 No.3

여러 가지 중수생산 공정중에서 백금촉매를 이용한 수소-중수소 동위원소 교환반응에 의해 중수를 생산하는 공정이 가장 효율적인 것으로 알려져 있다. 본 연구에서는 수소동위원소 교환반응에 이용될 수 있는 소수성 백금촉매를 개발하기 위하여, 담체로서 실리카라이트를 합성하였으며, 합성된 실리카라이트가 활성탄이나 ZSM-5보다 더 강한 소수성을 가지는 것을 보였다. 또한, 일반적인 함침법과 이온교환법을 이용하여 백금을 담지시켰으며, 여러 가지 방법으로 처리하여 제조한 백금담지 실리카라이트 촉매의 백금분산도를 수소흡착법을 이용하여 측정하였다. 함침법에 의해 제조된 촉매의 백금분산도는 매우 낮았으며, 이온교환법에 의해 제조된 촉매는 백금담지량은 적으나 분산도는 높음을 확인하였다. It is well known that the heavy water separation process using hydrogen isotope exchange reaction over the platinum catalyst is the most efficient. In this study, the Pt/silicalite catalysts were prepared and characterized by hydrogen adsorption in order to develop the hydrophobic platinum catalyst for hydrogen isotope exchange reaction. Silicalite was synthesized as support material and it was verified that silicalite is more hydrophobic than activated carbon and ZSM-5. Also the platinum was loaded on silicalite by conventional impregnation and ion-exchange method respectively. The platinum dispersion of Pt/silicalite catalysts was measured through hydrogen adsorption experiment. The dispersion is very low in the catalyst prepared by the impregnation method while it is very high with limited platinum content in the catalyst prepared by the ion-exchange method.

포스터 발표 - 무기재료분과 / 전기화학분과 / 촉매분과 : 비활성 알루미나 충전컬럼에서의 수소동위원소 분리특성

김광락,강희석,백승우,이성호,안도희,이한수,정흥석 ( Kwang Rag Kim,Hee Suk Kang,Seung Woo Paek,Sung Ho Lee,Do Hee Ahn,Han Soo Lee,Hong suk Chung ) 한국공업화학회 1997 한국공업화학회 연구논문 초록집 Vol.1990 No.3

N/A In the fields of operation and handling of the hydrogen isotope facility, and of management technology for the nuclear fusion source, gas chromatography has been used as one of the practical techniques for the separation and the enrichment of hydrogen isotopic gases including tritium. Chromatographic separation experiments of the hydrogen isotope mixture (hydrogen, deuterium and tritium) were carried out by use of a commercially available gas chromatograph. An aliquot of the gas sample was injected with a specially designed vacuum sampler into the stream of inert carrier gas which goes through the separation column at liquid nitrogen temperature. The complete separation of hydrogen isotopic molecules was observed with an alumina adsorbent partially deactivated by coating with 10% manganese chloride. In addition, fairly good separation conditions without appearance of the nuclear spin isomers in a shorter retention time, which would be useful for the practical applications of the hydrogen isotope separation and enrichment, were obtained.

비활성 알루미나 충전컬럼에서의 수소동위원소 분리특성

김광락,강희석,백승우,이성호,안도희,이한수,정흥석 ( Kwang Rag Kim,Hee Suk Kang,Seung Woo Paek,Sung Ho Lee,Do Hee Ahn,Han Soo Lee,Hong suk Chung ) 한국공업화학회 1997 한국공업화학회 연구논문 초록집 Vol.1997 No.0

N/A In the fields of operation and handling of the hydrogen isotope facility, and of management technology for the nuclear fusion source, gas chromatography has been used as one of the practical techniques for the separation and the enrichment of hydrogen isotopic gases including tritium. Chromatographic separation experiments of the hydrogen isotope mixture (hydrogen, deuterium and tritium) were carried out by use of a commercially available gas chromatograph. An aliquot of the gas sample was injected with a specially designed vacuum sampler into the stream of inert carrier gas which goes through the separation column at liquid nitrogen temperature. The complete separation of hydrogen isotopic molecules was observed with an alumina adsorbent partially deactivated by coating with 10% manganese chloride. In addition, fairly good separation conditions without appearance of the nuclear spin isomers in a shorter retention time, which would be useful for the practical applications of the hydrogen isotope separation and enrichment, were obtained.

상용 소수성 백금촉매의 제조비용 절감

안도희,백승우,강희석,최희주,정흥석 한국공업화학회 2003 응용화학 Vol.7 No.2

Wolsong Tritium Removal Facility(WTRF) is being constructed at Wolsong Nuclear Power Plant for reduction of the radiation hazards from tritium. The Liqiud Phase Catalytic Exchange (LPCE) process developed by KAERI and KEPRI was selected for the transfer process in WTRF. Approximately 2,000 litres of the hydrophobic platinum catalyst will be charged in the LPCE column. It was estimated that more than half of material cost for the catalyst preparation arised from H₂PtCl-(6) as a platinum precursor and high purity hydrogen gas as a reducing agent. In order to reduce material costs for the catalyst preparation, various catalysts were prepared and characterized using three kinds of H-(2)PtCl-(6) and two kinds of high purity hydrogen gas. It appears from the experiment that characteristics of the catalyst does not depend on both a kind of H₂PtCl_(6) and purity of hydrogen in the experimental conditions.

수소동위원소 운반용기 단열 해석

김광락,이민수,백승우,이성호,안도희,임성팔,정흥석 한국공업화학회 2003 응용화학 Vol.7 No.2

The immobilized hydrogen as a titanium hydride could be used in a stainless steel vessel for the long-term storage of hydrogen isotopes. The design analysis of a hydrogen isotope transport container with capacity of 0.5 MCi tritium was carried out to confirm the performance of the safely requirement. In order to verify that the radioactive transport container complies with the requirements for the B(U) type container stipulated in the MOST regulation of transport container, thermal analysis were made for normal condition and hypothetical accident conditions during transport. Thermal analysis with the Heating-7 code under conditions of 38℃ for 7 days and 800℃ for 30 minutes showed that the container complied with the requirement for B(U) type transport container.

트리튬 제염을 위한 수소 촉매 재결합 반응실험

김광락,강희석,백승우,안도희,이한수,최희주,이성호,정흥석 한국공업화학회 2000 응용화학 Vol.4 No.1

Safe handling of tritium is a current concern to be solved in the course of tritium removal facility that is being planed in the Wolsong nuclear power plant. Almost all tritium decontamination systems proposed for tritium removal facilities employ catalytic oxidation to water, followed by drying, to remove tritium from gas stream. A series of experiments have been conducted to assess the catalytic recombination characteristics of hydrogen in an air stream by using precious metal/alumina catalysts. The H₂ to H₂O fractional conversion was determined at various catalyst temperatures (25∼150℃) and flow rates (5∼1.5L/min.)

Pd/SDBC 촉매의 중수소 - 수증기간의 중수소 교환반응

이한수,김광락,이성호,백승우,정흥석,강희석,안도희 한국공업화학회 1998 응용화학 Vol.2 No.2

The Pd/SOBC catalysts were prepared in order to develop the wet-proofed catalyst for the deuterium exchange reaction between deuterated hydrogen and water vapor. The reactivity of the catalysts for the hydrogen isotope exchange reaction was tested under the boiling point of water. The experiments for the reaction were conducted to compare the efficiency of the Pd/SDBC catalyst with that of the Pd-Pt/SDBC catalysts. The experimental results showed that the Pd-Pt/SDBC had higher catalytic activity for the reaction than Pd/SDEC catalyst. In this study, it was found that the catalytic activity of Pd/SDBC catalyst was enhanced by the addition of small amounts of platinum.

감손 우라늄의 수소화 반응 특성

김광락,백승우,안도희,이성호,정흥석 한국공업화학회 2000 응용화학 Vol.4 No.1

Depleted uranium is produced in the process of nuclear fuel fabrication. The hydriding reaction of depleted uranium with hydrogen was carried out in order to develop the temporary storage medium of tritium gas. The depleted uranium was activated at 450℃ under vacuum conditions. The experimental results showed that the equilibrium pressure was lowered and the composition of uranium hydride was increased with lowering the reaction temperature. The similar tendencies were shown in the experiments using deuterium. The equilibrium pressure of deuterium was slightly higher than that of hydrogen. The uranium metal was converted to the powder after the hydriding reaction.