• 제목/요약/키워드: core power distribution

검색결과 295건 처리시간 0.025초

식물성 절연유 변압기의 냉각특성 변화에 따른 최고점온도 특성 해석 (Characteristic Analysis of Hot Spot Temperature according to Cooling Performance Variation of Natural Ester Transformer)

  • 김지호;이향범
    • 전기학회논문지P
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    • 제64권4호
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    • pp.236-240
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    • 2015
  • Natural ester has a higher biodegradability, flash and fire points, and a greater permittivity compared to conventional mineral oils. However, natural ester also has a higher pour point, viscosity, and water content. These characteristics hamper circulation and the electrical properties of oil-filled transformer. Thus, this paper applied electromagnetic-thermal-flow coupled analysis method to predict temperature distribution inside 154kV single phase power transformer using natural ester. It modeled in the actual appearance for the tank and winding of the power transformer to improve the accuracy of analysis and applied heat flow analysis that considered hydromechanics and heat transfer at the same time. It calculated the power loss, the main cause of temperature rise, from winding and core with electromagnetic analysis then used for the heat source for the heat flow analysis. It then compared the reasonability of result of measurement analysis based on the result acquired from temperature rise test using FBG sensor on the power transformer.

Performance Analysis of The KALIMER Breakeven Core Driver Fuel Pin Based on Conceptual Design Parameters

  • Lee Dong Uk;Lee Byoung Oon;Kim Young Gyun;Lee Ki Bog;Jang Jin Wook
    • Nuclear Engineering and Technology
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    • 제35권4호
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    • pp.356-368
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    • 2003
  • Material properties such as coolant specific heat, film heat transfer coefficient, cladding thermal conductivity, surface diffusion coefficient of the multi-bubble are improved in MACSIS-Mod1. The axial power and flux profile module was also incorporated with irradiation history. The performance and feasibility of the updated driver fuel pin have been analyzed for nominal parameters based on the conceptual design for the KALIMER breakeven core by MACSIS-MOD1 code. The fuel slug centerline temperature takes the maximum at 700mm from the bottom of the slug in spite of the nearly symmetric axial power distribution. The cladding mid-wall and coolant temperatures take the maximum at the top of the pin. Temperature of the fuel slug surface over the entire irradiation life is much lower than the fuel-clad eutectic reaction temperature. The fission gas release of the driver fuel pin at the end of life is predicted to be $68.61\%$ and plenum pressure is too low to cause cladding yielding. The probability that the fuel pin would fail is estimated to be much less than that allowed in the design criteria. The maximum radial deformation of the fuel pin is $1.93\%$, satisfying the preliminary design criterion ($3\%$) for fuel pin deformation. Therefore the conceptual design parameters of the driver fuel pin for the KALIMER breakeven core are expected to satisfy the preliminary criteria on temperature, fluence limit, deformation limit etc.

원자력 발전소 사고의 근사적인 베이지안 예측기법 (An Approximation Method in Bayesian Prediction of Nuclear Power Plant Accidents)

  • 양희중
    • 대한산업공학회지
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    • 제16권2호
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    • pp.135-147
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    • 1990
  • A nuclear power plant can be viewed as a large complex man-machine system where high system reliability is obtained by ensuring that sub-systems are designed to operate at a very high level of performance. The chance of severe accident involving at least partial core-melt is very low but once it happens the consequence is very catastrophic. The prediction of risk in low probability, high-risk incidents must be examined in the contest of general engineering knowledge and operational experience. Engineering knowledge forms part of the prior information that must be quantified and then updated by statistical evidence gathered from operational experience. Recently, Bayesian procedures have been used to estimate rate of accident and to predict future risks. The Bayesian procedure has advantages in that it efficiently incorporates experts opinions and, if properly applied, it adaptively updates the model parameters such as the rate or probability of accidents. But at the same time it has the disadvantages of computational complexity. The predictive distribution for the time to next incident can not always be expected to end up with a nice closed form even with conjugate priors. Thus we often encounter a numerical integration problem with high dimensions to obtain a predictive distribution, which is practically unsolvable for a model that involves many parameters. In order to circumvent this difficulty, we propose a method of approximation that essentially breaks down a problem involving many integrations into several repetitive steps so that each step involves only a small number of integrations.

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3개의 초전도 소자를 갖는 자속구속형 SFCL과 변압기형 SFCL의 특성 비교 (Comparison of Characteristics on the Flux-Lock and the Transformer Type SFCLs with Three Superconducting Units)

  • 이주형;최효상
    • 전기학회논문지P
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    • 제58권1호
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    • pp.79-84
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    • 2009
  • In order to increase the capacity of the superconducting fault current limiter(SFCL), the current and voltage grades of the SFCL must be increased. As a method for the increase of the current and voltage grades of the SFCL, we compared the various characteristics between the flux-lock type SFCL "With three superconducting units connected in series and the transformer type SFCL using the transformer with three secondary circuits. One of three superconducting units had not quenched in the flux-lock type SFCL. Therefore, the unbalanced power burden happened because of the voltage difference generated by unbalanced quenching between the superconducting units. In the meantime, the three superconducting units were all quenched in the transformer type SFCL using the transformer, and the voltage difference generated between the superconducting units was decreased. Therefore, the difference of critical characteristics was complemented by distribution of fault current in accordance with the turn's ratio between primary and secondary windings. The unbalanced power burden of the superconducting units was reduced due to flux-share between the superconducting units in the transformer. In conclusion, the capacity increment of the SFCL using a transformer was easier due to equal distribution of voltages generated by simultaneous quench of the superconducting units. We think that the characteristics is improved more because of the decrease of saturation in the iron core if the secondary winding is increased in the SFCL using the transformer.

Neutronic Benchmark 문제에 대한 B$\Phi$rrensen 모델응용 (B$\Phi$rrensen Model Computation for Neutronic Benchmark Problems)

  • Bub Dong Chung;Chang Hyo Kim;Chang Hyun Chung
    • Nuclear Engineering and Technology
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    • 제13권2호
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    • pp.73-84
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    • 1981
  • B$\Phi$rrensen은 3차원적 노심분석에 긴 시간이 요구되는 유한차분법의 대안으로서 경수형 원자로의 전체출력분포를 계산하는데 한가지의 coarse mesh 방법을 제안하였다. 이 방법은 계산시간이 매우 짧은 것으로 알려져 있지만. 그 계산의 정확도에 대한 것은 아직까지 알려져 있지 않다. 본 논문에서는 B$\Phi$rrensen의 방법을 IAEA benchmark 문제와 RIS$\Phi$ benchmark 문제에 적용시켜서 계산시간과 정확도에 대해서 고찰하였다. 두 문제에서 노심-반사체와의 경계조건과 B$\Phi$rrensen의 모델상수들의 개선으로 출력분포 계산의 정확도를 상당히 높힐 수 있었다.

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On-the-fly energy release per fission model in STREAM with explicit neutron and photon heating

  • Nhan Nguyen Trong Mai;Woonghee Lee;Kyeongwon Kim;Bamidele Ebiwonjumi;Wonkyeong Kim;Deokjung Lee
    • Nuclear Engineering and Technology
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    • 제55권3호
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    • pp.1071-1083
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    • 2023
  • The on-the-fly energy release per fission (OTFK) model is implemented in STREAM to continuously update the Kappa values during the depletion calculation. The explicit neutron and photon energy distribution, which has not been considered in previous STREAM versions, is incorporated into the existing on-the-fly model. The impacts of the modified OTFK model with explicit neutron and photon heating in STREAM on the power distribution, fuel temperature, and other core parameters during depletion with feedback calculations are studied using several problems from the VERA benchmark suit. Overall, the explicit heating calculation provides a better power map for the feedback calculations particularly when strong gamma emitters are present. Generally, the fuel temperature decreases when neutron and photon heating is employed because fission neutrons and gamma rays are transported away from their points of generation. This energy release model in STREAM indicates that gamma energy accounts for approximately 9.5%-10% of the total energy released, and approximately 2.4%-2.6% of the total energy released will be deposited in the coolant for the VERA 5, NuScale, and Yonggwang Unit 3 2D cores.

Landsat 열적외 영상자료를 활용한 대전시 열 환경 변화 모니터링 (Monitoring of Urban Thermal Environment Change in Daejun Using Landsat TIR Satellite Data)

  • 최진호;조현주;정환도
    • 환경영향평가
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    • 제22권5호
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    • pp.513-523
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    • 2013
  • This purpose of this work is to explore the characteristics of urban thermal environment distribution with the case of Daejeon. To do that, this work applied GIS Spatial Statistics to the LandSAT images gathered from 2000 to 2011. The urban thermal environment distribution at the time point of 2 showed high spatial autocorrelation. Therefore, it is judged that spatial autocorrelation is needed to increase the reliability and explanatory power of the characteristics of thermal environment distribution. In the case of the thermal in Daejeon, its positive clustering appeared high at the time point of 2, and its clustering in 2011 more gradually decreased than that in 2000 to 2011. In particular, given the decrease in the core H-H region, it was found that the thermal environment of Daejeon was greatly improved. However, since the rise in the region L-L means another changed like construction of a new city, it is judged that it is necessary to come up with a proper plan. It is considered that this analysis of the characteristics of urban thermal environment distribution in consideration of spatial autocorrelation L-L be useful for providing a fundamental material necessary for the policy and project of thermal environment improvement.

The Growth Strategy of Retail Companies: Focusing on New Stores Expansion of E-mart

  • Lee, Gi-Hwang;Kim, Sang-Cheol
    • 산경연구논집
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    • 제8권1호
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    • pp.15-22
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    • 2017
  • Purpose - Retail companies are turning from one type of retailer to multiple business categories through various reasons, such as taking advantage of existed types of retailers' channel distribution, information and know-how, and entering into new types of retailers. However, there is few research conducted about multiple type of retailers. Research design, data, and methodology - In this research, the references, data and new stores on E-mart will be collected. The dissertation, annual report, statistical data, land-book of E-mart will be also collected to confirm whether E-mart has made any acquisition towards another company. Results - There is a tendency to new stores expansion, store enlargement and prolonging the opening preparation of new stores, based on the core of new stores expansion of E-mart as a general supermarket type of retailers. Based on general supermarket type of retailers, E-mart begins to diversify its retail company's type of retailers. Conclusions - As a general supermarket which is the most important type of retailers, E-mart is expanding into SSM type of retailers to seek new power of growth while slowdown growth is shown in general supermarket type of retailers. The expansion into SSM type of retailers would be a wise option as a retail company, E-mart is able to keep growing in the future.

격납건물종합누설률시험 주기연장을 위한 웹기반 소외결말분석 프로그램 개발 및 적용 (Development of Web-based Off-site Consequence Analysis Program and its Application for ILRT Extension)

  • 나장환;황석원;오지용
    • 한국안전학회지
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    • 제27권5호
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    • pp.219-223
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    • 2012
  • For an off-site consequence analysis at nuclear power plant, MELCOR Accident Consequence Code System(MACCS) II code is widely used as a software tool. In this study, the algorithm of web-based off-site consequence analysis program(OSCAP) using the MACCS II code was developed for an Integrated Leak Rate Test (ILRT) interval extension and Level 3 probabilistic safety assessment(PSA), and verification and validation(V&V) of the program was performed. The main input data for the MACCS II code are meteorological, population distribution and source term information. However, it requires lots of time and efforts to generate the main input data for an off-site consequence analysis using the MACCS II code. For example, the meteorological data are collected from each nuclear power site in real time, but the formats of the raw data collected are different from each site. To reduce the efforts and time for risk assessments, the web-based OSCAP has an automatic processing module which converts the format of the raw data collected from each site to the input data format of the MACCS II code. The program also provides an automatic function of converting the latest population data from Statistics Korea, the National Statistical Office, to the population distribution input data format of the MACCS II code. For the source term data, the program includes the release fraction of each source term category resulting from modular accident analysis program(MAAP) code analysis and the core inventory data from ORIGEN. These analysis results of each plant in Korea are stored in a database module of the web-based OSCAP, so the user can select the defaulted source term data of each plant without handling source term input data.

The Iron loss Estimation of IPMSM According to Current Phase Angle

  • Cho, Gyu-Won;Kim, Dong-Yeong;Kim, Gyu-Tak
    • Journal of Electrical Engineering and Technology
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    • 제8권6호
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    • pp.1345-1351
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    • 2013
  • Variable iron loss as function of current phase angle of Interior Permanent Magnet Synchronous Motor(IPMSM) was calculated through Curve Fitting Method(CFM). Also, a magnetic flux density distribution of iron core according to current phase angle was analyzed, and an iron loss calculation was performed including harmonic distortion. The experiment was performed by production of non-magnetizing model for the separation of mechanical loss, and the iron loss was calculated by the measurement of input using power analyzer and output power using dynamometer. Some error was generated between experimental results and calculation value, but an iron loss diminution according to current phase angle followed a same pattern. So, errors were generated by measurement, vibration, noise, harmonic distortion loss, etc.