SiC is a material with excellent strength, heat resistance, and corrosion resistance. It is generally used as a material for SiC invertors, semiconductor susceptors, edge rings, MOCVD susceptors, and mechanical bearings. Recently, SiC single crystals for LED are expected to be a new market application. In addition, SiC is also used as a heating element applied directly to electrical energy. Research in this study has focused on the manufacture of heating elements that can raise the temperature in a short time by irradiating SiC-I2 with microwaves with polarization difference, instead of applying electric energy directly to increase the convenience and efficiency. In this experiment, Polydimethylsilane (PDMS) with 1,2 wt% of iodine is synthesized under high temperature and pressure using an autoclave. The synthesized Polycarbosilane (PCS) is heat treated in an argon gas atmosphere after curing process. The experimental results obtain resonance peaks using FT-IR and UV-Visible, and the crystal structure is measured by XRD. Also, the heat-generating characteristics are determined in the frequency band of 2.45 GHz after heat treatment in an air atmosphere furnace.

수용성 비이온고분자인 Polyvinylalcohol (PVA), Polyvinylpyrrolidone (PVP), Hydroxypropyl cellusoe (HPC)와 iodine과의 착물 형성에 대한 계면활성제의 영향을 알아보기 위해 Sodiumdodecylsulfate을 포함하는 수용액에서 이들 사이의 반응을 수행하였다. PVP와 HPC에서 tri-iodide band의 적색 이동에 의하여 착물이 만들어졌다는 것을 알게되었고, PVA-iodine 착물에서는 500 nm 부근에서 고유의 특색있는 띠를 나타내었다. SDS 계면활성제의 존재는 PVA-iodine 착물의 파괴를 가져왔고, 고유의 푸른색도 사라지게 만들었다. 그러나 SDS 단량체는 PVP, HPC와 iodine의 착물 형성을 도와주는 경향을 나타내었다. 고분자 용액에서 겔이 만들어지는 것을 방해하는 n-propanol은 고 분자-iodine 착물이 형성되는 것을 도와주었다. SDS가 있을 때와 없을 경우의 영향을 알아보기 위해 순 수한 HPC와 HPC-iodine 착물을 만들고 이들의 성질을 조사하였다.

Clostridium perfringens (C. perfringens) 와 Mycobacterium fortuitum (M. fortuitum)은 동물과 사람에서 심각한 질병과 관련이 있는 세균들로 알려져 있다. 본 연구에서는, povidoneiodine을 주성분으로 하는 소독제의 살균효과를 C. perfringes와 M. fortuitum을 대상으로 평가하였다. 소독제의 살균효과는 배지희석법을 이용하여, 대상 세균들을 4℃에서 소독제에 30분 동안 노출시킨 다음, 가장 낮은 소독제의 살균 희석배수를 결정하였다. 소독제는 경수와 유기물로 희석하였으며, 경수 조건에서, C. perfringes와 M. fortuitum에 대해 효과적인 소독제 희석배수는 각각 50과 80배이었다. 유기물 조건에서는, C. perfringes와 M. fortuitum에 대해 효과적인 소독제 희석배수는 모두 15배로 나타났다. 이상의 결과로부터, povidone-iodine을 주성분으로 하는 소독제는 C. perfringes와 M. fortuitum에 대해 살균효과를 갖는 것으로 확인되었으며, C. perfringes와 M. fortuitum에 의한 질병의 확산을 방지하기 위해 사용될 수 있을 것으로 사료된다.

올레핀/파라핀 분리 기술로 silver nanoparticles(AgNPs)를 운반체로 사용하여 보다 효과적으로 올레핀을 분리하는 고성능 올레핀 촉진수송 분리막을 제조하고자 하였다. 기존에 성능이 밝혀진 PVP/AgNPs/TCNQ 나노복합체 막에 추가적으 로 할로겐 물질을 첨가하여 AgNPs의 표면을 더 양극화시킴으로써 성능을 향상시키고자 하였다. 제조한 용액을 TEM과 EDS 로 분석해서 AgNPs의 형성과 iodine의 존재를 확인하였다. Propylene/propane 혼합기체의 분리 성능 실험을 통해 기존 PVP/AgNPs/TCNQ 나노복합체 분리막과 기체 분리 성능을 비교하였고, long-term stability 실험을 통해 분리막의 안정성을 조사하였다.

In order to understand the breakthrough behaviour of iodine vapours on impregnated carbon systems, an active carbon, 80 CTC grade, 12×30 BSS particle size and 1104 m2/g surface area, was impregnated with metal salts such Cu, Cr, Ag, Mo and Zn, and an organic compound Triethylene diamine (TEDA) to prepare different carbon systems such as whetlerite, whetlerite/TEDA, whetlerite/KI/KOH and ASZMT. The prepared adsorbents along with active carbon were characterized for surface area and pore volume by N2 adsorption at liquid nitrogen temperature. These carbon systems were compared for their CT (concentration X time) values at 12.73 to 53.05 cm/sec space velocities and 2 to 5 cm carbon column bed heights. The carbon column of 5.0 cm bed height and 1.0 cm diameter was found to be providing protection against iodine vapours up to 5.5 h at 3.712 mg/L iodine vapour concentration and 12.73 cm/sec space velocity. The study clearly indicated the adsorption capacities of carbon systems to be directly proportional to their surface area values. Dead layer with all the prepared carbon systems was found to be less than 2.0 cm indicating it to be minimum bed height to have protection against I2 vapours. Effect of carbon bed height and flow rate was also studied. The active carbon showed maximum protection at all bed heights and flow rates in comparison to all other impregnated carbon systems, showing that only physical adsorption is responsible for the removal of iodine vapours.

Reaction conditions and catalysts were investigated for direct CF3I synthesis. Optimum reaction temperature was determined by pyrolysis of CF3H and catalytic reactions. Reactions with changing oxygen concentration were performed. As a result, yield of CF3I increased with decreasing oxygen concentration. Catalytic activity was changed with the weight ratio of the used metal salts. This result was stemmed from the change in the pore size of activated carbon by the metal salts. The optimum reaction conditions were: 600℃, space velocity of 45hr-1, and with 7wt% KF/AC catalyst.

원자력 발전의 고온 가스로(high temperature gas-cooled reactor, HTGR)의 냉각제로 사용되는 He가스의 열에너지를 이용하여 물을 분해해서 수소를 생산하는 "열화학적 수소제조 IS프로세스"에 대해 설명하였다. 특히, 분리막 기술의 이용에 관한 연구를 중점으로 정리하였다. 고온 원자력 열에너지를 이용한 열화학적 수소 제조법은 실현 가능한 단계까지 왔다고 생각되며, 아직 연구 개발 과제가 많이 남아 있지만, 미래의 청정에너지 중의 하나인 수소를 대량 생산할 수 있는 가능성을 갖고 있다.

I-129 is one of the imporant nuclides that must be determined in the disposal process of radioactive waste in many countries. This radionuclide emits gamma-ray and x-ray photons within the energy range of 29 to 39 keV, consequently, an x-ray detector with high resolution performance is required for the analysis of I-129 activity. An n-type coaxial HPGe detector exhibits higher efficiency characteristics compared to a planar-type HPGe detector, however, its resolution is lower than a planar type. So it is difficult to completely deconvolute and fit the gamma-ray and xray peaks in the spectrum using a general gamma-ray spectrum analysis program such as GammaVision. To address this problem, in a previous study introduced the developed algorithm for the fitting and analysis of I-129 gamma-ray and x-ray spectum by fixing their emission ratios. In this study, we improved the algorithm by considering the variation of the efficiency in the HPGe spectrum, which reflects the actual HPGe crystal condition. And algorithm tests were performed using measured I-129 sample spectra with interfering nuclides acting as background curve are introduced.

Wasteform is the first barrier to prevent radionuclide release from repositories into the biosphere. Since leaching rates of nuclides in wasteform significantly impact on safety assessment of the repository, clarifying the leaching behavior is critical for accurate safety assessment. However, the current waste acceptance criteria (WAC) of the Gyeongju repository only evaluates leachability indexes for Cs, Sr, and Co, which are tracers for nuclear power plant waste streams. Furthermore, ANS 16.1, the current leaching test method used in WAC, applies deionized water (DI) as leachant. However, the interactions between wasteform and groundwater environment in the repository may not be reflected. Therefore, it is necessary to review the current leaching test method and nuclides that may require the extra evaluation of leachability beyond the Cs, Sr, and Co. Tc and I are key nuclides contributing to high radioactive dose in safety assessment due to their high mobility and low retardation factor. The groundwater conditions within the repository, such as pH and Eh significantly affect the chemical form of Tc and I. For example, Tc in H2O system tends to form hydroxide precipitates in neutral pH condition and TcO4 - in strong alkaline environments according to the Pourbaix diagram. In case of I, it generally exists in the form of I-, while it exists as IO3 - as Eh increases. Although the current leaching test at the Gyeongju repository applies DI as a leachant, the actual repository is expected to have a highly alkaline environment with a substantial amount of various ions in the groundwater. Consequently, the leaching behavior in the ANS 16.1 test and the actual disposal condition is different. Thus, it is necessary to analyze the leaching behavior of Tc and I with reflecting the actual disposal environment. In this study, the leaching behavior of Tc and I is investigated by following ANS 16.1 leaching test method. The solidified waste specimens containing 10 mmol of Re and I were manufactured with cement, which is widely used as a solidification material. Re was applied instead of Tc, which has similar chemical behavior to Tc, and NH4ReO4 and NaI were used as surrogates for Re and I. As a leachant, deionized water and cement-saturated groundwater were prepared and the concentration of nuclides in the leachant is analyzed by ICP-OES. As the result of this study, experimental data can be applied to improve the WAC and disposal concentration standards in the future.

The spent fuels derived from the nuclear reactor facilities may be finally disposed in a deep underground below 500 m. It majorly has uranium with minor iodine, which is a typical anionic radionuclide. In particular, radioiodine has higher mobility from its spent fuel source. It has been well known that it could freely pass through a compacted bentonite that is one of underground engineering barriers that are used to retard some nuclide’s migration from the spent fuel. We installed a small laboratory apparatus in an anaerobic glove box imitating such an underground repository and evaluated the iodine mobility in compacted bentonites with or without copper. Some copper-bearing bentonites were prepared in two types, a copper ion-exchanged form and a copper nanoparticle-mixed one. In our study, we tried to find an effect of sulfate that has an ability to retard mobile iodine from the compacted bentonite for a long-term period. Conclusively, we found an effective way to limit the iodine release from the compacted bentonite. This condition can be achievable by exchanging the bentonite interlayer cations with copper ions or by simply mixing copper nanoparticles with bentonite powder. In those cases, soluble iodine can be easily immobilized as a solid phase (i.e., marshite (CuI)) by combining with copper via the geochemical role of sulfate and indigenous SRB (sulfate reducing bacteria) of bentonite.