• Nuclear Engineering and Technology
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• 제54권6호
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• pp.1972-1981
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• 2022

A typical ferritic/martensitic (F/M) steel sheet was subjected to pulsed laser surface remelting (LSR) and corrosion test in lead-bismuth eutectic (LBE) at 550 ℃. There present two modification zones with distinct microstructures in the LSRed specimen: (1) remelted zone (RZ) consisting of both bulk δ-ferrite grains and martensitic plates and (2) heat-affected zone (HAZ) below the RZ, mainly composed of martensitic plates and high-density precipitates. Martensitic transformation occurs in both the RZ and the HAZ with the Kurdjumov-Sachs and Nishiyama-Wassermann orientation relationships followed concurrently, resulting in scattered orientations and specific misorientation characteristics. Hardnesses of the RZ and the HAZ are 364 ± 7 HV and 451 ± 15 HV, respectively, considerably higher than that of the matrix (267 ± 3 HV). In oxygen-saturated and oxygen-depleted LBE, thicknesses of oxide layers developed on both the as-received and the LSRed specimens increase with prolonging corrosion time (oxide layers always thinner under the oxygen-depleted condition). The corrosion resistance of the LSRed F/M steel in oxygen-saturated LBE is improved, which can be attributed to the grain-refinement accelerated formation of dense Fe-Cr spinel. In oxygen-depleted LBE, the growth of oxide layers is very low with both types of specimens showing similar corrosion resistance.

• Journal of the Korean Wood Science and Technology
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• 제31권6호
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• pp.73-82
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• 2003

Various forest humic substances were collected at different climate regions with different forest types, and adsorption of heavy metals such as Cu(II), Zn(II), Cd(II) and Cr(III) were characteristically conducted to obtain optimal adsorption conditions and to evaluate the removal efficiency of heavy metals by each forest humic substance. The adsorption isotherms for Cu(II), Zn(II), Cd(II) and Cr(III) conformed to Langmuir's equation. In the stirred reactor, the removal efficiencies of Cu(II), Zn(II) and Cd(II) by forest humic substances were more than 90% but that of Cr(III) was less than 60%. The adsorption capacities of heavy metals in the stirred reactor were considerably varied depending on the type of forest humic substances. Among humic substances, the one from deciduous forest at subtropical region showed the highest removal efficiency for Cu(II). There was no significant difference in removal efficiency by each heavy metal depending on reaction temperature ranged from 20 to 50oC except for Cr(III), and the adsorptions of Cu(II), Zn(II) and Cd(II) were occurred rapidly in the incipient stage within 10 min, while Cr(III) needed more reaction time to be adsorbed. The stirred and packed bed column reactors showed similar adsorption characteristics of heavy metals by humic substances, but the removal efficiency was considerably higher in the packed bed column reactor than in the stirred reactor. Therefore, in actual operation process, a continuous packed bed column reactor was more economical.

• 청정기술
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• 제15권2호
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• pp.130-136
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• 2009

상용촉매인 Johnson Matthey사 KATALCO 83-3 촉매를 이용하여 마이크로 채널 반응기 (micro-channel reactor: MCR) 형태에 따른 메탄올 수증기 개질반응을 통한 수소제조반응 특성 연구를 수행하였다. 반응온도 200${\sim}$300$^{\circ}C$, 공간속도 3,000${\sim}$10,000 $hr^{-1}$, 촉매 크기 0.05${\sim}$2.2 mm 조건을 갖는 고정층 반응기에서 반응활성 실험을 수행한 결과, 촉매 크기 0.35 mm에서 최적의 반응활성을 나타났다. 이 결과를 토대로 stacked bed, boat bed 등 마이크로 채널 반응기 형태에 따른 반응활성을 연구한 결과, stacked bed type 마이크로 채널 반응기가 더 좋은 반응활성을 가짐을 알 수 있었다.

• Korean Chemical Engineering Research
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• 제54권5호
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• pp.612-620
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• 2016

산화 칼슘 수용액을 통해 이산화탄소를 포집하는 수성 광물 탄산화 공정은 안정적으로 이산화탄소를 고립시킬 뿐 아니라 생성물의 부가 가치를 기대할 수 있는 대표적인 CCU (Carbon Capture & Utilization) 기술이다. 이 공정의 핵심은 고체 반응물인 산화칼슘의 용해 속도를 최대로 높이는 것인데, 이를 위해 반응기 전체에 고체 반응물이 균일하게 분포되도록 혼합하는 적절한 반응기의 설계가 필요하다. 본 논문에서는 하루에 40ton의 이산화탄소 포집이 가능한 파일럿 규모의 광물 탄산화 반응기를 대상으로, 반응기의 내부 구조 설계에 따라 고체 반응물의 분산도가 어떻게 변하는지에 대해 전산 유체 역학적 모델링(Computational Fluid Dynamics (CFD) modeling)을 통해 연구하였다. 교반 탱크 반응기(stirred tank reactor) 형태를 기반으로 외부 구조는 고정한 상태에서 교반기의 종류/갯수/지름/유격/회전 속도, 칸막이의 높이/너비를 변수로 선정하여 다양한 조합의 경우(case)들을 해석하였다. 각 설계 변수에 대한 민감도를 분석함으로써 각 변수의 영향을 파악하고, 중요한 변수를 판별할 수 있었다. 동시에 고체 부피 분율(solid volume fraction)의 높이 방향 표준 편차가 0.001에 가까운 균일한 분포를 만들 수 있는 내부 설계안을 제안하였다.

• Strategy21
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• 통권41호
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• pp.261-293
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• 2017

Nuclear power is a way of attaining an enormous amount of energy with relatively small amount of resources and after it has been introduced to the submarine since 1954, there are approximately 150 of nuclear powered submarine currently on a mission around the world. This is due to the maneuverability, mountability and covertness of nuclear submarines. However, there are other tasks, not only the high level of nuclear technology that are needed to be dealt with in order to construct nuclear powered submarine. The biggest task of all is to secure the enriched uranium. Accordingly, this research is about the way of enriching and securing the nuclear fuel that are used in the nuclear submarine with the characteristics, merits and demerits of the nuclear submarine. Due to the fact that the pressurized water reactor in South Korea is the reactor that was originally built for the development of nuclear powered submarine, many parts is designed to be suitable for the submarine propulsion. However, in order to apply this to submarine it is needed to consider additional requests such as the position of reactor, accident-coping system, radioactive covering, reactor output adjustment and ship's pitch and roll in order to apply this to submarine. Nuclear submarines have much higher speed based on the powerful propulsion in comparison with diesel-electric submarine and also have bigger loading area. Besides, there is no need to snorkel and they also have advantages in covertness with the multi-noise proof system. The nuclear technology in South Korea has seen the dramatic development since 1962 and in 1998 reached to the level that we have succeeded in the localization of nuclear plant and exported the world-class one-piece small-sized reactor (SMART) to UAE. To operate these reactors, we import the whole quantity of low-enriched uranium and having our own uranium enrich facility is not probable because of the budget and international regulations. With the ROK/US nuclear agreement revised on 2015 November, the enrichment of uranium that are available without special permission has changed up to 20%. According to the assumption that we use the 20% enrichment of Uranium on U.S. virginia class submarine, it is necessary to change the fuel after 11 years and it will cause additional cost of 1 billion dollars. But the replace period by the uranium's enrichment rate is not fixed so that it is possible to change according to the design of reactor. Therefore, I would like to make a suggestion on two types of design concepts of nuclear submarine that can be operated for 30 years without nuclear fuel change by using the 20% enriched uranium from ONNp.First of all, it is possible by increasing the size of reactor by 3 times and it results in the 1,000t increase of the weight. And secondly, it is by designing the one piece reactor to insert devices such as steam turbine, condenser into the inside of nuclear core like the Rubis class submarines of France.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2003년도 춘계학술대회
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• pp.13-18
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• 2003

Reduced activation ferritic steel, JLF-1 steel (Fe-9Cr-2W-V-Ta), is one of the promising candidate materials for fusion reactor applications. Fracture toughness ($J_IC$) and tensile tests were carried out at room temperature and elevated temperature ($400^{\circ}C$). Two types of CT specimen were prepared to examine the effect of rolling direction on the fracture toughness of JLF-1 steel. Four types of tensile specimen were also prepared to investigate the property by the rolling direction and welding. The Micro Vickers hardness was measured at various distances of a cross section of the TIG joints of JLF-1 steel according to the heating history of each position. Finally, the fracture surface was observed by scanning electron microscopy (SEM).

• Journal of Advanced Marine Engineering and Technology
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• 제24권3호
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• pp.79-87
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• 2000

This paper describes experimental investigations of helium-air exchange flow through openings with vertical partitions. Such exchange flows may occur following rupture accident of stand pipe in high temperature gas cooled reactor. Exchange flow rates are investigated experimentally by using partitioned opening and opening with extended partition to assess fluids interference of the exchange flow at the stand pipe rupture accident. A tests vessel with the two types of opening on top of test cylinder is used in the experiments. An estimation method of mass increment is developed and applied to measure the exchange flow rate. A technique of flow visualization by Mach-Zehnder interferometer is provided to recognize the exchange flows. Amplitude and progress of interference fringes of the flows are observed and used as a support in comparison with the exchange flow rates. Flow passages of upward flow of the helium and downward flow of the air for both two types of the opening are separated by inserted partition within the opening, but in the case of partitioned opening, unseparated flow is formed at the opening entrance and the two flows interface. The exchange flow rate for the partitioned opening is not greater than that of the opening with extended partition because of the fluids interference at the entrance of opening. Finally, the fluids interference at the opening entrance is found to be one of important factors on the helium-air exchange flow rate.

• 한국결정성장학회지
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• 제15권4호
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• pp.135-140
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• 2005

Thermal-fluid analysis was performed to understand the thermal behavior in the horizontal CVD reactor thereby to design a susceptor which has a uniform deposition rate during silicon EPI growing. Four different types of susceptor designs, standard (no hole susceptor), hole $\sharp$1 (240 mm), hole $\sharp$2 (150 mm) and hole $\sharp$3 (60 mm), were simulated by CFD (Computational Fluid Dynamics) tool. Temperature, gas flow, deposition rate and growth rate were calculated and analyzed. The degree of flatness of EPI wafer loaded on the susceptor was computed in terms of silicon growth rate. The simulation results show that the temperature and thermal distribution in the wafer are greatly dependent on inner diameter of hole susceptor and demonstrate that the introduction of hole in the susceptor can degrade wafer flatness. Maximum temperature difference appeared around holes. As the diameter of the hole decreases, flatness of the wafer becomes poor. Among the threes types of susceptors with the hole, optimal design which resulted a good uniform flatness ($5\%$) was obtained when using hole $\sharp$1.

• Journal of Advanced Marine Engineering and Technology
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• 제21권4호
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• pp.372-380
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• 1997

This paper describes experimental investigations of helium-air exchange flows through parti¬tioned opening and two-opening. Such exchange flows may occur following rupture accident of stand pipe in high temperature gas cooled reactor. A test vessel with the two types of small open¬ing on top of test cylinder is used for experiments. An estimation method of mass increment is developed and applied to measure the exchange flow rate. A technique of flow visualization by Mach-Zehnder interferometer is provided to recognize the exchange flows. In the case of exchange flow through the partitioned opening, flow passages of upward flow of the helium and downward flow of the air within the opening are separated by vertical partition, and the two flows interact out of entrance and exit of the opening. Therefore, an experiment of the exchange flow through two-opening is made to investigate effect of the fluids interaction of the partitioned opening sys¬tem. As a result of comparison of the exchange flow rates between the two types of the opening system, it is found that the exchange flow rate of the two-opening system is larger than that of the partitioned opening system due to absence of the effect of fluids interaction. Finally, the fluids interaction between the upward and downward flows through the partitioned opening is found to be an important factor on the helium-air exchange flow.

• 한국병원경영학회지
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• 제5권1호
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• pp.156-175
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• 2000

This study was designed to find out the relations between the major investment decision-making behaviors and profitability of the hospital. A total of 57 hospitals were analyzed on this study. The major findings were as follows; 1. Among the types of the investment decision-making, major factors affecting the profitability were where the top management belongs among the defender, analyzer, prospector, and reactor type. Other factors were whether or not hospital analyzes which is more economical between the purchase by cash and lease of the medical equipment and whether or not hospital changes the decision before the actual investment. 2, Among the types of the investment decision-making, major factors affecting the financial structure and efficient operation of the assets were ranking of the priority and whether or not hospitals can get enough revenue and cash flow when hospitals have to borrow a big amount of fund from outside. 3. Among the financial indices regarding the financial stability, major factor affecting the profitability was fixed assets to long-tenn capital. Other factors affecting the financial structure and efficient operation of the assets were value added to medical equipment, normal profit to medical equipment, liability to total assets, current ratio, value added to payroll expenses. 4. Investment decision-making behaviors are partially influencing on the financial structure and efficient operation of the assets. However it was proved that the profitability was the most influencial factor than other factors related with the operation of the hospital. 5. To improve the irrational investment decision-making behaviors strategic management system should be introduced, and the top mamagement's investment decision-making style should be changed from reactor and analyser styles to prospector and reactor ones.