• Title/Summary/Keyword: Micro-reactor

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Direct Strength Evaluation of the CVD SiC Coating of TRISO Coated Fuel Particle with Micro Hemi Spherical Shell Configuration (마이크로 반구 쉘 형상의 화학증착 탄화규소 TRISO 코팅층의 파괴강도 직접평가)

  • Lee, Hyeon-Keun;Kim, Do-Kyung
    • Journal of the Korean Ceramic Society
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    • v.44 no.7
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    • pp.368-374
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    • 2007
  • CVD-SiC coating has been introduced as a protective layer in TRISO nuclear fuel particle of high temperature gas cooled reactor (HTGR) due to its excellent mechanical stability at high temperature. In order to prevent the failure of the TRISO particles, it is important to evaluate the fracture strength of the SiC coating layer. It is needed to develop a new simple characterization technique to evaluate the mechanical properties of the coating layer as a pre-irradiation step. In present work, direct strength measurement method with the specimen of hem i-spherical shell configuration was suggested. The indentation experiment on a hemisphere shell with a plate indenter was conducted. The fracture strength of the coating layer is related with the critical load for radial cracking of the shell. The finite element analysis was used to drive the semi-empirical equation for the strength measurement. The SiC hemispherical shells were successfully recovered from the section-grinding of TRISO coated particle and successive heat treatment in air. The strength of CVD-SiC coating layer was evaluated from the experimentally measured critical load during the indentation on SiC hemisphere shell. Weibull diagram of fracture strength was also constructed. This study suggested a new strength equation and experimental method to measure the fracture strength of CVD-SiC coating of TRISO coated fuel particles.

Removal of Cadmium. Copper and Chromium Ions in Aqueous Solution using Water in Oil Micro-Emulsion (W/O 마이크로에멀젼을 이용한 수용액중의 카드뮴, 구리 및 크롬이온의 분리제거)

  • Lee, Sung-Sik;Lee, Eun-Joo;Kim, Hyung-Jun;Kim, Jong-Hwa
    • Journal of Korean Society of Environmental Engineers
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    • v.22 no.6
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    • pp.1021-1026
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    • 2000
  • The removal of cadmium, copper and chromium ions was carried in a phase transfer reactor using W/O(water in oil) microemulsion containing sodium di[2-ethylhexyl] sulfosuccinate(AOT) and isooctane system. Removal efficiencies and mass transfer rate of $Cd^{2+}$, $Cu^{2+}$ and $Cr^{3+}$ were increasing with increasing pH of aqueous solution. However, $Cr^{6+}$ was not extracted by W/O microemulsion with AOT/isooctane system. It was found that removal of heavy metal ions were required an attractive electrostatic interaction between the metal ions and W/O microemulsion. The relationship between mass transfer rate. Jo of $Cd^{2+}$, $Cu^{2+}$ and $Cr^{3+}$ and pH of aqueous solution by W/O microemulsion suggested.

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Decomposition Study of Acetaldehyde by Metal-oxide Catalysts (금속산화물 촉매에 의한 $CH_3CHO$의 분해반응 연구)

  • Lee, Chang-Seop;Kim, Young-Eun;Choi, Sung-Woo
    • Journal of the Korean Institute of Gas
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    • v.11 no.2 s.35
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    • pp.25-30
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    • 2007
  • The catalysts for decomposition reaction of acetaldehyde were investigated. The catalysts were prepared with transition metal Ni, Mo, Al on ${\gamma}-Al_2O_3$ support by impregnation method. Physio-chemical properties of catalysts were characterized by SEM-EDS, XRD, XPS, BET and TPR techniques. The conversion efficiency of catalysts for acetaldehyde was measured in the temperature range of $150{\sim}500^{\circ}C$ by GC through the micro reactor system. The 8 wt% $Ni/{\gamma}-Al_2O_3$ was found to be the most active catalyst of mono-metal catalysts tested, and the 1-3 wt% $Ni-Al/{\gamma}-Al_2O_3$ showed higher conversion efficiency than other bimetallic catalysts.

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HIGH BURNUP FUEL TECHNOLOGY IN KOREA

  • Song, Kun-Woo;Jeong, Yong-Hwan;Kim, Keon-Sik;Bang, Je-Geon;Chun, Tae-Hyun;Kim, Hyung-Kyu;Song, Kee-Nam
    • Nuclear Engineering and Technology
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    • v.40 no.1
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    • pp.21-36
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    • 2008
  • High bum-up fuel technology has been developed through a national R&D program, which covers key technology areas such as claddings, $UO_2$ pellets, spacer grids, performance code, and fuel assembly tests. New cladding alloys were developed through alloy designs, tube fabrication, out-of-pile test and in-reactor test. The new Zr-Nb tubes are found to be much better in their corrosion resistance and creep strength than the Zircaloy-4 tube, owing to an optimized composition and heat treatment of the new Zr-Nb alloys. A new fabrication technology for large grain $UO_2$ pellets was developed using various uranium oxide seeds and a micro-doping of Al. The uranium oxide seeds, which were added to $UO_2$ powder, were prepared by oxidizing and heat-treating scrap $UO_2$ pellets. A $UO_2$ pellet containing tungsten channels was fabricated for a thermal conductivity enhancement. For the fuel performance analysis, new high burnup models were developed and implemented in a code. This code was verified by an international database and our own database. The developed spacer grid has two features of contoured contact spring and hybrid mixing vanes. Mechanical and hydraulic tests showed that the spacer grid is superior in its rodsupporting, wear resistance and CHF performance. Finally, fuel assembly test technology was also developed. Facilities for mechanical and thermal hydraulic tests were constructed and are now in operation. Several achievements are to be utilized soon by the Korea Nuclear Fuel and thereby contribute to the economy and safety of PWR fuel in Korea

Effects of Proton Irradiation on the Microstructure and Surface Oxidation Characteristics of Type 316 Stainless Steel (양성자 조사가 316 스테인리스강의 미세조직과 표면산화 특성에 미치는 영향)

  • Lim, Yun-Soo;Kim, Dong-Jin;Hwang, Seong Sik;Choi, Min Jae;Cho, Sung Whan
    • Corrosion Science and Technology
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    • v.20 no.3
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    • pp.158-168
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    • 2021
  • Austenitic 316 stainless steel was irradiated with protons accelerated by an energy of 2 MeV at 360 ℃, the various defects induced by this proton irradiation were characterized with microscopic equipment. In our observations irradiation defects such as dislocations and micro-voids were clearly revealed. The typical irradiation defects observed differed according to depth, indicating the evolution of irradiation defects follows the characteristics of radiation damage profiles that depend on depth. Surface oxidation tests were conducted under the simulated primary water conditions of a pressurized water reactor (PWR) to understand the role irradiation defects play in surface oxidation behavior and also to investigate the resultant irradiation assisted stress corrosion cracking (IASCC) susceptibility that occurs after exposure to PWR primary water. We found that Cr and Fe became depleted while Ni was enriched at the grain boundary beneath the surface oxidation layer both in the non-irradiated and proton-irradiated specimens. However, the degree of Cr/Fe depletion and Ni enrichment was much higher in the proton-irradiated sample than in the non-irradiated one owing to radiation-induced segregation and the irradiation defects. The microstructural and microchemical changes induced by proton irradiation all appear to significantly increase the susceptibility of austenitic 316 stainless steel to IASCC.

4H-SiC bulk single crystal growth using recycled powder (재생 분말을 활용한 4H-SiC 벌크 단결정 성장)

  • Yeo, Im Gyu;Lee, Jae Yoon;Chun, Myong Chuel
    • Journal of the Korean Crystal Growth and Crystal Technology
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    • v.32 no.5
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    • pp.169-174
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    • 2022
  • This study is to verify the feasibility of SiC single crystal growth using recycled SiC powder. The fundamental physical properties such as particle size, shape, composition and impurities of the recycled powder were analyzed, and the sublimation behavior occurring inside the reactor were predicted using the basic data. As a result of comprehensive judgment, the physical properties of the recycled powder were suitable for single crystal growth, and single crystal growth experiments were conducted using this. 100 mm 4H-SiC single crystal ingot with a height of 25 mm was grown without polytype inclusion. In the case of micro-pipe density was 0.02 ea/cm2 and resistivity characteristics was 0.015~0.020 ohm·cm2, commercial level quality was obtained, but additional analysis related to dislocation density and stacking faults is required for device application.

A Study on the In situ Regeneration Effects of Commercial Deactivated SCR Catalyst (상용 탈질 SCR 폐촉매의 현장 재생 효과 고찰)

  • Park, Hea-Kyung;Jun, Min-Kee;Kim, Moon-Chan
    • Journal of Korean Society of Environmental Engineers
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    • v.34 no.10
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    • pp.664-670
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    • 2012
  • A study on the in situ regeneration effect of commercial deactivated SCR catalyst which had been exposed to the off gas from the heavy oil fired power plant for a long time was carried out in a simulated in situ conditions by washing with distilled water and various acid solutions in a short time. The catalytic performance test of the regenerated SCR catalysts was carried out in the micro reactor with simulated off gas of the heavy oil fired power plant and all prepared catalysts were characterized by BET, Porosimeter, EDX (Energy Dispersive X-ray spectrometer) and ICP (Inductively Coupled Plasma) to investigate correlations between catalytic activity and surface characteristics of them. The characterization results of the regenerated catalysts showed that the specific surface area was restored 95% more than that of fresh catalyst. Under this study, the activity of the regenerated catalysts with acid solution (3~6 M) without using ultrasonic wave in a simulated in situ conditions was restored 90% more than that of the fresh catalyst. It was found that improved activity of regenerated catalyst was caused by removing the deactivating materials from the surface of the deactivated SCR catalyst through acid washing.

The Effect of Post-Bond Heat Treatment on Tensile Property of Diffusion Bonded Austenitic Alloys (확산 접합된 오스테나이트계 재료의 인장특성에 미치는 후열처리의 영향)

  • Hong, Sunghoon;Kim, Sung Hwan;Jang, Changheui;Sah, Injin
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.39 no.12
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    • pp.1221-1227
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    • 2015
  • Diffusion bonding is the key manufacturing process for the micro-channel type heat exchangers. In this study, austenitic alloys such as Alloy 800HT, Alloy 690, and Alloy 600, were diffusion bonded at various temperatures and the tensile properties were measured up to $650^{\circ}C$. Tensile ductility of diffusion bonded Alloy 800HT was significantly lower than that of base metal at all test temperatures. While, for Alloy 690 and Alloy 600, tensile ductility of diffusion bonded specimens was comparable to that of base metals up to $500^{\circ}C$, above which the ductility became lower. The poor ductility of diffusion bonded specimen could have caused by the incomplete grain boundary migration and precipitates along the bond-line. Application of post-bond heat treatment (PBHT) improved the ductility close to that of base metals up to $550^{\circ}C$. Changes in tensile properties were discussed in view of the microstructure in the diffusion-bonded area.

Formation of GaN microstructures using metal catalysts on the vertex of GaN pyramids (금속촉매를 이용한 GaN 피라미드 꼭지점 위의 마이크로 GaN 구조 형성)

  • Yun, W.I.;Jo, D.W.;Ok, J.E.;Jeon, H.S.;Lee, G.S.;Jung, S.K.;Bae, S.M.;Ahn, H.S.;Yang, M.
    • Journal of the Korean Crystal Growth and Crystal Technology
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    • v.21 no.3
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    • pp.110-113
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    • 2011
  • In this paper, we propose a new method for the fabrication of GaN microstructures formed only on the vertex of GaN pyramid by using of metal catalysts. GaN pyramidal structures were selectively grown on 3 ${\mu}m$ $SiO_2$ dot patterns followed by thin film deposition of Au and Cr only on the vertex area of the GaN pyramids with precisely controlled photolithography. After the metal deposition, the samples were loaded in the MOVPE reactor for the growth of GaN microstructures for 10 minutes. Temperature for the growth of the GaN microstructures was changed from $650^{\circ}C$ to $750^{\circ}C$. Rod type GaN microstructures were grown in the direction of vertical to the six {1-101} facets and the shape of the GaN microstructures was changed depend on the type of metal.

A Study on Dissolve and Remove Analysis of Organic Chemicals Using a Mixed Method of Advanced Oxidation and Micro Filtering - Water Drinking Point - (고도산화와 정밀여과의 혼성공법을 이용한 유기화학물질의 분해 및 제거분석에 관한 연구 - 먹는 물을 중심으로 -)

  • An, Tai-Young;Jun, Sang-Ho;Ahn, Tae-Seok;Han, Mi-Ae;Hur, Jang-Hyun;Pak, Mi-Young
    • Membrane Journal
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    • v.17 no.2
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    • pp.99-111
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    • 2007
  • It is impossible to remove toxic organic substances that are recognized as a cancer caused suspicious element in drinking water using the conventional water purification method. This study introduces groundwater into a reaction chamber as an effective amount of water to process this water using a mixed method of AOP oxidation and M/F membrane and purifies it as a desirable level by artificially mixing such toxic substances in order to effectively process the water. Based on this fact, this study configures an optimal operation condition. The VOCs existed in toxic substances was investigated as a term of phenol and toluene, and agricultural chemicals were also investigated as a term of parathion, diazinon and carbaryl. The experiment applied in this study was performed using a single and composite soolution. In the operation condition applied to fully dissolve and remove such substances, the amount of $H_2O_2$ injected in the process was 150 mL of a fixed quantity, the value of pH was configured as $5.5{\sim}6.0$, the temperature was controlled as a range of $12{\sim}16^{\circ}C$, the dissolved amount of ozone was applied more than 5.0 mg/L, the reaction time was determined as an optimal condition, such as $30{\sim}40$ minutes, and the segregation membrane in the same reactor was determined for acquire water drinking of large quantity using a pore size of $0.45{\mu}m$ M/F membrane.