• 제목/요약/키워드: CONDENSER

검색결과 1,031건 처리시간 0.029초

A STUDY ON THE MICROSTRUCTURES OF THE AMALGAM ALLOYS AND AMALGAMS (치과용 아말감합금 및 아말감의 마세구조에 관한 연구)

  • Yeon, Sang-Heum;Lee, Chung-Sik;Lee, Myung-Jong;Um, Chung-Moon
    • Restorative Dentistry and Endodontics
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    • 제21권1호
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    • pp.87-105
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    • 1996
  • The purpose of this study is to investigate the characteristics of the compositions and phases of amalgam alloys and amalgams by using EMPA and X-ray diffractometer. Each specimen was made from Caulk Fine Cut Clow copper lathe cut amalgam), Caulk Spherical (low copper spherical amalgam), Tytin (high copper unicorn position amalgam), Dispersally (high copper admixed amalgam) and Valiant (Palladium enriched amalgam). For preparing amalgam alloys, Tytin and Valiant were used as powder forms and the others were used as tablet forms after being polished with polishing machine. For preparing amalgams, each amalgam alloy and Hg were measured, and triturated by mechanical amalgamater according to user's instructions. After triturating, the triturated mass was inserted to cylindrical metal mold and simultaneously adapted by cylindrical condenser with same diameter and condensed by Instron universal testing machine with 80kg pressure & 1mm/min speed. Each specimen was removed from the metal mold and stored at room temperature for a week. The specimen was polished with the same polishing machine for amalgam alloy. For observation of microstructure and analysis of composition of amalgam alloys and amalgams, EMPA was used to get secondary electron images, backscattered images and characteristic X-ray images of Ag, Sn, Cu, Zn, Hg. To analyze compositions of amalgam alloys and amalgams, X-ray diffractometer was used. Amalgam alloys were scanned at the range of 2${\theta}$ of 30-$85^{\circ}$ and the speed of $4^{\circ}$/min with Cuka line and amalgams were scanned at the range of 2${\theta}$ of 28-$44^{\circ}$ and the speed of $4^{\circ}$/min with Cuka line. By comparing obtained d(distance between surfaces) and d of expected phases and atoms in amalgam alloys and amalgams in ASTM card, phases and atoms were identified. The results were as follows, 1. In Caulk Fine Cut amalgam alloy typical ${\gamma}$ phase was shown, and in amalgam, ${\gamma}$, ${\gamma}_1$ and ${\gamma}_2$ phases were observed. 2. In Caulk Spherical amalgam alloy ${\gamma}$, Ag, Cu and $\varepsilon$ phases were shown, and in amalgam ${\gamma}$, ${\gamma}_1$, ${\gamma}_2$ and $\eta$ phases were observed. 3. In Tytin amalgam alloy ${\gamma}$, Cu and $\varepsilon$ phases were shown, and in amalgam ${\gamma}$, ${\gamma}_1$, $\eta$ and $\varepsilon$ phases were observed. 4. In Dispersalloy ${\gamma}$, Ag, Cu and $\varepsilon$ phases were shown, and in amalgam ${\gamma}$, ${\gamma}_1$, $\eta$ and $\varepsilon$ phases were observed. 5. In Valiant alloy ${\gamma}$, Cu and e phases were shown, and in amalgam ${\gamma}$, ${\gamma}_1$, $\eta$ and $\varepsilon$ phases were observed.

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A Study on the Improvement for Cycle Efficiency of Closed-type OTEC (폐쇄형 해양온도차발전 사이클 효율 향상 방안)

  • Lee, Ho-Saeng;Kim, Hyeon-Ju;Jung, Dong-Ho;Moon, Deok-Soo
    • Journal of Advanced Marine Engineering and Technology
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    • 제35권1호
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    • pp.46-52
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    • 2011
  • A study on the improvement for cycle efficiency of closed-type ocean thermal energy conversion (OTEC) was studied to obtain the basic data for the optimal design of cycle. For that, OTEC cycle with a generator, a reheater and a multi-turbine was simulated and analyzed. The basic thermodynamic model for OTEC is Rankine cycle and the surface seawater of $26^{\circ}C$ and deep seawater of $5^{\circ}C$ were used for the heat source of evaporator and condenser, respectively. Ammonia is used as the working fluid. The cycle efficiency increased when generator is added with 0.9 generator effectiveness. When the reheater and multi-turbine are applied in the basic cycle, the cycle efficiency showed 3.14% and the capacity of heat exchanger decreased for same total cycle power. For the OTEC cycle with the generator, the reheater and the multi-turbine showed the highest cycle efficiency and increased the efficiency by more than 6.5% comparing with the basic OTEC cycle.

Characteristics of Ondol Heating Load for the Determination of Heat Pump Power (열펌프 시스템의 규모 결정을 위한 온돌난방부하 특성)

  • 노정근;백은기;송현갑
    • Journal of Biosystems Engineering
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    • 제28권3호
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    • pp.217-224
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    • 2003
  • To find out heating load and to determine the power of heat pump compressor for the Ondol room heating the COP of heat pump, the variation of Ondol room air temperature, the variation of ambient temperature and power consumption of heat pump are analyzed. The results from this study were summarized as follows: 1. The COP of the heat pump in close loop decreased as the ambient air temperature. The COP was 2.26 when the temperature difference of condenser was $20\pm3^{\circ}C$. 2. The Ondol surface temperature was $25\pm3^{\circ}C$ when the hot water of $40^{\circ}C$ was supplied from hot water storage tank to the Ondol and the temperature difference between the Ondol surface and the room air temperature was $7~8^{\circ}C$. 3. The ratio of thermal conduction heating load to total heating load in Ondol heating space was found to be 83% and ratio of ventilation heating load was 17%. Therefore, the thermal conduction heating load was confirmod to be a major heating load in Ondol heating space. 4. In case of the ambient temperature of $3.2^{\circ}C$, the efficiency of heat exchange of Ondol heating system was 85%. 5. The heating load per Ondol heating surface area and volume of Ondol room space were theoretically analyzed. In case of the room temperature of $20^{\circ}C$ and the ambient temperature of $-3.2~3.8^{\circ}C$, the heating load per Ondol surface area was 115.8~167.6kJ/h ㆍ㎥ and per Ondol mom space volume was 50.2~72.7kJ/h ㆍ㎥. 6. The compressor power of heat pump fur the Ondol room heating could be determined with the heating load analyzed in this study In case of the Ondol room air temperature of 17~2$0^{\circ}C$ and the ambient temperature of -5~3.8$^{\circ}C$, the compressor power of heat pump per Ondol surface area was analyzed to be $2.3\times10^{-2}psm^2$, and per volume of Ondol room space $1.0\times10^{-2}1.4\times10^{-2}ps/m^2$ps.

Separation of chlorine in a uranium compound by pyrohydrolysis and steam distillation, and its determination by ion chromatography (열가수분해 및 수증기증류에 의한 우라늄 화합물 중 염소 분리 및 이온크로마토그래피 정량)

  • Kim, Jung-Suk;Lee, Chang-Hun;Park, Soon-Dal;Han, Sun-Ho;Song, Kyu-Seok
    • Analytical Science and Technology
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    • 제23권1호
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    • pp.45-53
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    • 2010
  • For the determination of chlorine in uranium compound, analytical methods by using a steam distillation and a pyrohydrolysis have been developed. The steam distillation apparatus was composed of steam generator, distilling flask and condenser etc. The samples were prepared with an aliquot of LiCl standard solution and a simulated spent nuclear fuel. A sample aliquot was mixed with a solution containing 0.2 M ferrous ammonium sulfate-0.5 M sulfamic acid 3 mL, phosphoric acid 6 mL and sulfuric acid 15 mL. The chloride was then distilled by steam at the temperature of $140^{\circ}C$ until a volume of $90{\pm}5\;mL$ is collected. The pyrohydrolysis equipment was composed of air introduction system, water supply, quartz reaction tube, combustion tube furnace, combustion boat and absorption vessel. The chloride was separated from powdered sample which is added with $U_3O_8$ accelerator, by pyrohydrolysis at the temperature of $950^{\circ}C$ for 1 hour in a quartz tube with a stream of air of 1 mL/min supplied from the water reservoir at $80^{\circ}C$. The chlorides collected in each absorption solution by two methods was diluted to 100 mL and measured with ion chromatography to determine the recovery yield. For the ion chromatographic determination of chlorine in molten salt retained in a metal ingot, the chlorine was separated by means of pyrohydrolysis after air and dry oxidation, and grinding for the sample.

Separate type heat pipe performance comparison by the heat exchanger shapes (열교환기 형상에 따른 분리형 히트파이프 성능 비교)

  • Jeon, Sung-Taek;Cho, Jin-Pyo
    • Journal of the Korea Academia-Industrial cooperation Society
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    • 제17권12호
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    • pp.723-729
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    • 2016
  • This study compared fin-tube and parallel-flow heat pipes for their sensible heat exchange rate, heat recovery amount, and air-side pressure drop. Tests were done with different refrigerant charging rates of 40-60% vol. and air flow rates of 300-1,400. The sensible heat exchange rate was highest for both types of heat pipes at a working fluid charge of 40% vol. and low flow rate. For the parallel-flow heat pipe, the 60% vol. charge is too high and results in a low sensible heat exchange rate. The reason is that the thicker liquid film of the tube wall deteriorates the heat transfer effect. Hence, the optimal charging rate is 40 to 50% vol. The evaporator heat pipe has a larger air-side pressure drop than the condenser section heat pipe. The reason is considered to be condensation water arising from the evaporator surface. Compared to the fin-tube heat pipe, the parallel-flow heat pipe showed better performance with a working fluid charging rate of 48%, volume of 41%, and an air-side pressure drop about 37%.

The effects of non-condensable gas on condensation heat transfer on a super-hydrophobic surface tube (초소수성 코팅 튜브에서의 비응축가스 영향에 대한 응축 열전달 연구)

  • Ji, Dae-Yun;Kim, Daeho;Lee, Kwon-Yeong
    • Journal of the Korea Academia-Industrial cooperation Society
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    • 제19권4호
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    • pp.517-524
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    • 2018
  • This purpose of this research is to observe the influence of non-condensable gas (NCG) on a horizontal super-hydrophobic aluminum tube and compare it with a bare aluminum tube. To achieve super-hydrophobic characteristics, an aluminum tube was coated with a Self-Assembled Monolayer (SAM). The overall heat transfer coefficient U was used to represent the condensation performance. The NCG mass fraction was the main variable, and its range was 0.08 to 0.45. The condensation performance of the SAM tube and bare tube increased with decreasing mass fraction of NCG. The SAM tube showed 1.9 to 2.5 times larger dropwise condensation performance than the bare tube. When the mass fraction of NCG decreased in the SAM tube, the rate of increase of the SAM tube was lower because flooded condensation occurred. In addition, filmwise condensation occurred in the SAM tube when more active condensation was generated, and its performance was lower than that of the bare aluminum tube. The flooded and filmwise condensation in the SAM tube is explained by the pinning effect. In conclusion, controlling the condition of the condenser is necessary to improve the condensation performance by surface modification a SAM.

Experimental Study of Co-firing and Emission Characteristics Fueled by Sewage Sludge and Wood Pellet in Bubbling Fluidized Bed (기포 유동층 반응기를 이용한 하수슬러지 및 우드펠렛 혼소에 관한 연소 특성 분석 및 비교)

  • Lee, Youngjae;Kim, Jongmin;Kim, Donghee;Lee, Yongwoon
    • Clean Technology
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    • 제23권1호
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    • pp.80-89
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    • 2017
  • The bubbling fluidized bed (BFB) reactor with a diameter of 0.1 m and a height of 1.2 m was used for experimental study of co-firing and emission characteristics fueled by sewage sludge (SS) and wood pellet (WP). The facility consists of a fluidized bed reactor, feeding system, cyclone, condenser and gas analyzer, The mean particle diameter and minimum fluidization velocity are $460{\mu}m$ and $0.21ms^{-1}$ respectively. SS produced from Korea and WP from Canada were examined. The various mixing ratios of WP were 20, 50, and 80% based on HHV. The equivalence ratio of 1.65, reactor temperature of $800^{\circ}C$, air flow rate of $100Lmin^{-1}$, and fluidization number of 4 were fixed in the BFB experiment. In TGA, the range of combustion temperature of SS was wider than that of WP. It represents that the combustibility of WP is higher than that of SS. The BFB reactor temperature was maintained between 800 and $900^{\circ}C$. CO emission of SS was high because of lower combustibility. $NO_X$ and $SO_X$ formation of SS were higher than that of WP since high nitrogen and sulfur contents of SS. CO, $NO_X$, and $SO_X$ formation were suppressed as the mixing ratio of WP was increased. The slagging and fouling tendencies show high in all test conditions.

The characteristics of nuclear powered submarine and the use of enriched uranium (원자력 추진 잠수함의 특성과 농축우라늄 사용)

  • Jang, Jun-Seop
    • 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.

Performance analysis of a cooling system with refrigerant in a marine absorption refrigerator (선박용 흡수식 냉동기의 냉매적용 냉각 시스템 성능 분석)

  • Yun, Sang-Kook
    • Journal of Advanced Marine Engineering and Technology
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    • 제40권4호
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    • pp.282-287
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    • 2016
  • Recently in order to protect the ocean environment and to reduce energy consumption, shipbuilders have been developing highly economized ships. This research analyzed the possibility of adopting the onshore absorption refrigerator to offshore ships having a cooling system with refrigerant by using the waiste heat of the engine jacket cooling water instead of compression refrigerators. The results showed that R236fa could be a suitable medium for absorbing the heat of the absorber and condenser in an absorption refrigerator. The cooling system using R236fa achieved a high COP of 0.798, which is 15% and 5% higher than an air cooling system with a cooling tower and a water cooling system with a heat exchanger, respectively. The cooling system with R236fa achieved high efficiency with a 25% reduction in flow rate of LiBr solution and only 15.7% flow rate of cooling medium as compared to the water cooling system. The heating of sea water by the engine jacket water flowing out from the generator can prevent the crystallization of LiBr solution due to the low temperature of sea water.

Study on the Property of Guided Wave Signal Analysis according to Defect Shape of Small Size (소구경 튜브 결함 형태에 따른 유도초음파 신호 해석 특성에 관한 연구)

  • Gil, Doo-Song;Ahn, Yeon-Shik;Jung, Gye-Jo;Park, Sang-Gi;Kim, Yong-Gun
    • Journal of the Korean Society for Nondestructive Testing
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    • 제32권4호
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    • pp.410-417
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    • 2012
  • Currently domestic thermal and nuclear power plants are comprised of many type's condenser and steam generator tubes to produce the electricity of good quality. There are some methods to inspect these tubes in the event that several defects were discovered in these facilities. Among many non-destructive methods, we used guided wave to inspect the soundness of tubes, because this method is very fast to detect the defect and very simple to install the equipment and also, can inspect up to the long range at a fixed point. Also, this method has a drawback that does not detect a very small size defect. So, we made an effort to overcome this drawback through the experimentation and signal analysis according to the size and shape of the defect through the manufacture of various artificial cracks capable to generate within the small size tube in the study and we anticipate that these detect limits can be overcome along with the development of the signal processing and manufacturing technology of the sensor for the inspection.