• 제목/요약/키워드: Nuclear Program

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스탄디나비아 노인용 코하우징 주민의 이주동기 (Moving Motivation of Senior Cohousing Inhabitants in Scandinavian Countries)

  • 최정신
    • 한국주거학회:학술대회논문집
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    • 한국주거학회 2003년도 정기총회 및 추계학술대회
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    • pp.307-312
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    • 2003
  • The purpose of this study was to find out the moving motivation of senior cohousing inhabitants in Scandinavian countries, which experienced change of typical nuclear family structure and higher vocational activity rates of women, earlier than East Asian countries. Cohousing schemes were evolved as an alternative housing to reduce housework for working women, and to reduce loneliness of elderly people by promoting active mutual relationship among inhabitants in the community. This paper described why the elderly moved to senior cohousing in Sweden and Denmark. The project was carried out by social survey. 935 postal questionnaires were sent from April to May 2002 to 28 senior cohousing communities throughout Denmark and Sweden. Of those, 536 replies (57.3%) were collected and analyzed by SPSS program. 19 moving motivations were discussed connected with the variables such as characteristics of residents, community-initiative, and dwelling size. As a result ideology of senior cohousing, wanting to be free from housing management and physical attraction of the building could be interpreted as main reasons to make inhabitants move to senior cohousing community. The important variables affecting moving motivation were found out as living situation and community-initiative. This findings could be used for some information to architects, designers and decision makers who intend to develope senior cohousing projects in the near future in Korea as well as Scandinavian countries.

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Inhibitory effect of Yongdamsagantang water extract on IL-6 and nitric oxide production in lipopolysaccharide-activated RAW 264.7 cells

  • Lim, Jin-Ho;Lee, Jong-Rok;Kim, Sang-Chan;Jee, Seon-Young
    • Advances in Traditional Medicine
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    • 제7권3호
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    • pp.321-329
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    • 2007
  • The present study was conducted to evaluate the effect of Yongdamsagantang (YST) on the regulatory mechanism of cytokines and nitric oxide (NO) for the immunological activities in RAW 264.7 cells. After the treatment of YST water extract, cell viability was measured by MTT assay, and NO production was monitored by measuring the nitrite content in culture medium. Inducible nitric oxide synthase (iNOS) and phospholylation of inhibitor of nuclear factor kappa B alpha ($p-I{\kappa}B{\alpha}$) were determined by Immunoblot analysis, and levels of cytokine were analyzed by sandwich immunoassays. Results provided evidences that YST inhibited the production of NO. iNOS, and interleukin-6, and the activation of $p-I{\kappa}B{\alpha}$ in RAW 264.7 cells activated with lipopolysaccharide. These findings showed that YST could have some anti-inflammatory effects which might play a role in therapy in Gram-negative bacterial infections.

한울 3호기 주급수 배관 용접부 육안검사 경험 (Experience in Visual Testing of the Main Feed Water Piping Weld for Hanul Unit 3)

  • 윤병식;문균영;김용식
    • 한국압력기기공학회 논문집
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    • 제11권1호
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    • pp.74-78
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    • 2015
  • Nuclear power plant steam generator that is one of the main component has several thousands of thin tubes. And the steam generator tube is subject to damage because of the severe operation conditions such as the high temperature and pressure. Therefore periodic inspections are conducted to ensure the integrity of steam generator component. Hanul unit 3 also has been inspected in accordance with in-service inspection program and is scheduled to be replaced for exceeding the plugging rate which was recommended by manufacturer. During the steam generator replacement activity, we found several clustered porosity on inner surface of main feed water pipe. Additionally crack-like indications were found at weld interface between base material and weld of main feed water pipe. This paper describes the field experience and visual testing results for inner surface of main feed water pipes. The destructive test result had shown that these indications were porosities which were caused by manufacturing process not by operation service.

Feeding the Abalone Haliotis discus hannai with the Seaweed Eisenia bicyclis Allows the Accumulation of Phlorotannins

  • Bangoura, Issa;Chowdhury, Muhammad Tanvir Hossain;Getachew, Paulos;Cho, Ji-Young;Hong, Yong-Ki
    • Fisheries and Aquatic Sciences
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    • 제18권2호
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    • pp.165-171
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    • 2015
  • Abalone containing phlorotannins is produced by feeding the phlorotannin-rich brown seaweed Eisenia bicyclis after 4 days of starvation. Reverse-phase high-performance liquid chromatography (RP-HPLC) was used to isolate and quantify phlorotannins, which were identified by mass spectrometry and [$^1H$]-nuclear magnetic resonance to be the P1 compound, 7-phloroeckol, and eckol. When E. bicyclis was used as feed, P1 compound accumulated to an average of 1.60 mg/g dry weight of abalone muscle tissue after 18 d, 7-phloroeckolol to 0.21 mg/g after 16 d, and eckol to 0.22 mg/g after 12 d. Saccharina japonica was used as a control feed, and the abalone showed little or no accumulation of phlorotannins in muscle tissue. Feed consumption and growth rate were very similar when either E. bicyclis or S. japonica was fed for 20 d. Half-maximal reductions in the levels of P1 compound, 7-phloroeckol, and eckol accumulation were attained in 1.5, 1.9, and 3.4 days, respectively, after the feed was switched from E. bicyclis to S. japonica. Value-added abalone containing bioactive phlorotannins can be produced by simply changing the feed to the phlorotannin-rich E. bicyclis 18 d prior to harvesting.

핵연료 조사시험용 캡슐 구조물의 좌굴 및 진동특성 (Buckling and Vibration Characteristics of the Capsule for Nuclear Fuel Irradiation Test)

  • 강영환;김봉구;류정수;김영진;최명환
    • 한국소음진동공학회논문집
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    • 제14권8호
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    • pp.741-748
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    • 2004
  • The vibration and buckling characteristics of the capsule for fuel irradiation test are studied. The natural frequencies of the capsule in air and under water are obtained by modal testing and finite element (FE) analysis using ANSYS program, and accelerations with flow are measured to estimate the compatibility with the operation requirement of the HANARO reactor. The experimental fundamental frequencies of the capsule in the x and z direction are 8.5 Hz and 8.75 Hz in air, and 7.5 Hz and 7.75 Hz under water, respectively. The maximum amplitude of accelerations under the normal operating condition is measured as 11.0 m/s$^2$ that is within the allowable vibrational limit(18.99 m/s$^2$) of the reactor structure. Also, the maximum displacement at 100% flow is calculated as 0.13 mm which is not interference with other nearby structures. FE analysis results show that the natural frequencies are found to be similar to those of the modal testing when three supporting parts are considered as simply supported conditions. From the buckling analysis, when the loading tool is applied, the critical buckling load of the capsule is 233 N.

간극효과를 고려한 증기발생기 전열관의 3차원 유한요소해석 (3-D Finite Element Analyses of Steam Generator Tubes Considering the Gap Effects)

  • 조영기;박재학
    • 한국압력기기공학회 논문집
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    • 제7권4호
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    • pp.51-56
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    • 2011
  • Steam generator is one of the main equipments that affect safety and long term operation in nuclear power plants. Fluid flows inside and outside of the steam generator tubes and induces vibration. To prevent the vibration the tubes are supported by AVB (anti vibration bar). When the steam generator tube contact to AVB, it is damaged by the accumulation of wear and corrosion. Therefore studies are required to determine the effects of the gap between the steam generator tube and AVB. In order to obtain the stress and the displacement distributions of the steam generator tube, three dimensional finite element analyses were performed by using the commercial program ANSYS. Using the calculated the stress and the displacement distributions, the static residual strength of the steam generator tube can be evaluated. The results show that the stress and displacement of the steam generator tube increase significantly compared with the results from a zero-gap model.

원자로 노심 쉬라우드의 조사유기응력부식균열 민감도 예비 분석 (Preliminary Analysis on IASCC Sensitivity of Core Shroud in Reactor Pressure Vessel)

  • 김종성;박창제
    • 한국압력기기공학회 논문집
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    • 제15권2호
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    • pp.58-63
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    • 2019
  • This paper presents preliminary analysis and results on IASCC sensitivity of a core shroud in the reactor pressure vessel. First, neutron irradiation flux distribution of the reactor internals was calculated by using the Monte Carlo simulation code, MCNP6.1 and the nuclear data library, ENDF/B-VII.1. Second, based on the neutron irradiation flux distribution, temperature and stress distributions of the core shroud during normal operation were determined by performing finite element analysis using the commercial finite element analysis program, ABAQUS, considering irradiation aging-related degradation mechanisms. Last, IASCC sensitivity of the core shroud was assessed by using the IASCC sensitivity definition of EPRI MRP-211 and the finite element analysis results. As a result of the preliminary analysis, it was found that the point at which the maximum IASCC sensitivity is derived varies over operating time, initially moving from the shroud plate located in the center of the core to the top shroud plate-ring connection brace over operating time. In addition, it was concluded that IASCC will not occur on the core shroud even after 60 years of operation (40EFPYs) because the maximum IASCC sensitivity is less than 0.5.

크리이프를 고려한 매스콘크리트의 수화열에 대한 온도응력 해석 (Thermal Stress Analysis on ike Heat of Hydration for Mass Concrete Considering Creep Effect)

  • 김진근;이종대;김국한
    • 한국전산구조공학회:학술대회논문집
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    • 한국전산구조공학회 1992년도 가을 학술발표회 논문집
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    • pp.67-72
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    • 1992
  • The heat of hydration of cement causes the internal temperature rise at early age, particulary in massive concrete structures such as a footing of nuclear reactor building or a dam. As the result of the temperature rise and restraint of foundation, the thermal stress may induce cracks in concrete. Therefore, the prediction of the thermal stress is very important in the design and construction stages in order to control the cracks developed in massive concrete structures. And, in case of young concrete, creep effect by the temperature load is larger than That of old concrete. Thus the effect of creep must be considered for checking the cracks, serviceability, durability and leakage. This study is composed of two items. The first, it is to develop a finite element program which is capable of simulating the temperature history in mass concrete. The second, when the thermal stress of mass concrete structures considering creep is calculated by using the modified elastic modulus due to the inner temperature change. It is shown that the analytical results of this study is in comparably good agreement with JCI's analytical results.

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HDAC4 Regulates Muscle Fiber Type-Specific Gene Expression Programs

  • Cohen, Todd J.;Choi, Moon-Chang;Kapur, Meghan;Lira, Vitor A.;Yan, Zhen;Yao, Tso-Pang
    • Molecules and Cells
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    • 제38권4호
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    • pp.343-348
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    • 2015
  • Fiber type-specific programs controlled by the transcription factor MEF2 dictate muscle functionality. Here, we show that HDAC4, a potent MEF2 inhibitor, is predominantly localized to the nuclei in fast/glycolytic fibers in contrast to the sarcoplasm in slow/oxidative fibers. The cytoplasmic localization is associated with HDAC4 hyper-phosphorylation in slow/oxidative-fibers. Genetic reprogramming of fast/glycolytic fibers to oxidative fibers by active CaMKII or calcineurin leads to increased HDAC4 phosphorylation, HDAC4 nuclear export, and an increase in markers associated with oxidative fibers. Indeed, HDAC4 represses the MEF2-dependent, PGC-$1{\alpha}$-mediated oxidative metabolic gene program. Thus differential phosphorylation and localization of HDAC4 contributes to establishing fiber type-specific transcriptional programs.

증기발생기 유로홈막힘 사진판독 알고리즘 개발 (Development of the S/G TSP Clogging Image Analysis Algorithm)

  • 조남철;김왕배;문찬국
    • 한국압력기기공학회 논문집
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    • 제7권3호
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    • pp.8-14
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    • 2011
  • The clogging of the flow area at the tube support plates(TSPs), especially at the upper TSPs results in the water level oscillation of a steam generator during normal operation. A reduction of the TSP flow area causes to increase in pressure drop within the two-phase flow zone, which destabilizes the boiling flow through the tube bundle. This phenomenon was occasionally observed at a few domestic and foreign nuclear power plants. One of the methods for defining the flow area clogging is visual inspection, which is the most effective inspection method. The results of the visual inspection for TSPs' flow area are clogging images on TSPs' quartrefoil lobes. These images are complexly distorted due to lens aberration and external factors like the distance to a subject and angle etc. In this work, we developed the analysis algorithm for clogging image of the TSP flow area of steam generators. For this purpose, we designed an image verification device applicable to the camera employed in the field for visual inspection and then, we demonstrated the validity of image analysis algorithm by using this device and commercial autoCAD program.