• 제목/요약/키워드: Nuclear structure

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적응 PIF Gain 및 가변구조 제어기를 사용한 비선형 모델에 의한 원자로의 Robust Control (Nonlinear Model-Based Robust Control of a Nuclear Reactor Using Adaptive PIF Gains and Variable Structure Controller)

  • Park, Moon-Ghu;Cho, Nam-Zin
    • Nuclear Engineering and Technology
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    • 제25권1호
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    • pp.110-124
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    • 1993
  • 적응 비례-적분-추정 (PIF) gain 및 가변구조 제어기를 사용하는 비선형 모델에 의한 하이브리드 제어방법 (NHC)이 개발되었다. 이 제어기는 모델의 불확실성에 대해 robust한 성질을 가지며 단일 입-출력 비선형 시스템의 추적제어 (tracking control)에 응용된다. 이 방법의 특징은 제어기가 각각 특정 역할을 수행하는 4개 부분으로 구성되는 것이다. 즉, 적응 P-I-F 및 가변구조 제어기로 구성된다. Lyapunov의 제 2방법으로 결정된 적응 PIF gain에 의한 제어성능 확보 및 모델의 불확실도를 평가하여 피이드백 함으로써 모델의 불확실성에 대해 robust한 제어기를 구성하였다. 가변구조 제어기는 PIF gain이 적절히 결정되지 않은 상태인 초기의 오차증가를 제어하기 위해 도입되었다. 새로 개발된 NHC방법을 원자로의 출력변동 제어에 응용한 결과 기존의 모델을 이용한 제어방법 (model-based controller)들에 비해 제어성능이 크게 개선되었다.

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하부지지구조물 바닥판 구멍크기 변경이 원자로 노심 입구 유량분포에 미치는 영향에 관한 수치해석 (Numerical Analysis of the Effect of Hole Size Change in Lower-Support-Structure-Bottom Plate on the Reactor Core-Inlet Flow-Distribution)

  • 이공희;방영석;정애주
    • 대한기계학회논문집B
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    • 제39권11호
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    • pp.905-911
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    • 2015
  • 본 연구에서는 하부지지구조물 바닥판의 외곽영역에 위치한 구멍의 크기 변경(구멍 직경 감소)이 노심 입구 유량분포에 미치는 영향을 조사하기 위해 상용 전산유체역학 소프트웨어인 ANSYS CFX R.15를 사용하여 계산을 수행하였고, 기존 바닥판 구멍 형태에 대한 계산 결과와 비교하였다. 결론적으로 하부지지구조물 바닥판의 외곽영역에 위치한 구멍의 직경 감소를 통해 노심 입구에서 보다 균일한 유량 분포를 얻을 수 있었다. 따라서 원자력 규제측면에서 볼 때 본 연구에서 제시한 하부지지구조물 바닥판의 외곽영역 구멍 형태의 설계 변경은 연료집합체의 기계적 건전성 및 노심 열적여유도를 향상시킬 수 있다는 측면에서 바람직할 것으로 판단된다.

Depositon of Transparent Conductive Films by a DC arc Plasmatron

  • Penkov, O.V.;Plaksin, V. Yu.;Joa, S.B.;Kim, J.H.;LEE, H.J.
    • 한국진공학회:학술대회논문집
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    • 한국진공학회 2009년도 제38회 동계학술대회 초록집
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    • pp.480-480
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    • 2010
  • In the present work, we studied effect of the deposition parameters on the structure and properties of ZnO films deposited by DC arc plasmatron. The varied parameters were gas flow rates, precursor composition, substrate temperature and post-deposition annealing temperature. Vapor of Zinc acetylacetone was used as source materials, oxygen was used as working gas and argon was used as the cathode protective gas and a transport gas for the vapor. The plasmatron power was varied in the range of 700-1,500 watts. Flow rate of the gases and substrate temperature rate were varied in the wide range to optimize the properties of the deposited coatings. After deposition films were annealed in the hydrogen atmosphere in the wide range of temperatures. Structure of coatings was investigated using XRD and SEM. Chemical composition was analyzed using x-ray photo-electron spectroscopy. Sheet conductivity was measured by 4-point probe method. Optical properties of the transparent ZnO-based coatings were studied by the spectroscopy. It was shown that deposition by a DC Arc plasmatron can be used for low-cost production of zinc oxide films with good optical and electrical properties. Sheet resistance of 4 Ohms cm was achieved after the deposition and 30 min annealing in the hydrogen at $350^{\circ}C$. Elevation of the substrate temperature during the deposition process up to $350^{\circ}C$ leads to decreasing of the film's resistance due to rearrangement of the crystalline structure.

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FACTORS OF GROUNDWATER FLUCTUATION IN SHIN KORI NUCLEAR POWER PLANTS IN KOREA

  • Hyun, Seung Gyu;Woo, Nam C.;Kim, Kue-Young;Lee, Hyun-A
    • Nuclear Engineering and Technology
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    • 제45권4호
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    • pp.539-552
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    • 2013
  • To establish an aging management plan considering seawater influx and changes in groundwater within nuclear power plant sites, the characteristics of groundwater flow must be understood. This study investigated the characteristics of groundwater flow within the site and analyzed groundwater level recorded by monitoring wells to evaluate groundwater flow characteristics and elements that affected these characteristics for supplying the information to conduct the appropriate aging management for ensuring the safety of the safety-related structures in Shin Kori Unit 1 and 2. The increase in groundwater level during the wet season results from high sea-level conditions and the large amount of precipitation. As a result of the analysis of groundwater distribution and change characteristics, the site could be divided into a rainfall-affected area and a tide-affected area. First, the rainfall-affected area can further be divided into areas that are affected simultaneously by excavation, backfill, and a permanent dewatering system. Secondly, areas that are not affected by excavation, or the dewatering system, or by structure arrangement and excavation. Analysis of the spectrum for wells affected by tides resulted in confirmation of the M2 component (12.421 hr) and S2 component (12.000 hr) of the semidiurnal tides, and the O1 component (25.819 hr) of the diurnal tides. In the cross-correlation results regarding tides and groundwater levels, the lag time occurred diversely within 1-3 hours by the effect of the well location from sea, the distribution of the backfill material with depth, and the concrete structure.

면진 원전구조물의 전도거동과 면진시스템 특성에 대한 샘플링 기법이 정지거리에 미치는 영향 (Effect of Rocking Behavior of Isolated Nuclear Structures and Sampling Technique for Isolation-System Properties on Clearance-to-stop)

  • 한민수;홍기증;조성국
    • 한국지진공학회논문집
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    • 제19권6호
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    • pp.293-302
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    • 2015
  • ASCE 4 requires that a hard stop be built around the seismic isolation system in nuclear power plants. In order to maintain the function of the isolation system, this hard stop is required to have clearance-to-stop, which should be no less than the 90th-percentile displacements for 150% Design Basis Earthquake (DBE) shaking. Huang et al. calculated clearance-to-stop by using a Latin Hypercube Sampling technique, without considering the rocking behavior of the isolated structure. This paper investigates the effects on estimation of clearance-to-stop due to 1) rocking behavior of the isolated structure and 2) sampling technique for considering the uncertainties of isolation system. This paper explains the simplified analysis model to consider the rocking behavior of the isolated structure, and the input earthquakes recorded at Diablo Canyon in the western United States. In order to more accurately approximate the distribution tail of the horizontal displacement in the isolated structure, a modified Latin Hypercube Sampling technique is proposed, and then this technique was applied to consider the uncertainty of the isolation system. Through the use of this technique, it was found that rocking behavior has no significant effect on horizontal displacement (and thus clearance-to-stop) of the isolated structure, and the modified Latin Hypercube Sampling technique more accurately approximates the distribution tail of the horizontal displacement than the existing Latin Hypercube Sampling technique.

NUCLEAR SPIRALS IN NEARBY GALAXIES

  • ANN HONG BAE
    • 천문학회지
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    • 제38권2호
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    • pp.121-124
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    • 2005
  • High resolution images of the nuclear regions of nearby galaxies show that nuclear spirals are preponderant in normal galaxies as well as in active galaxies. These nuclear spirals, especially the grand-design nuclear spirals are found to be formed by the gas flow driven by the bar. Hydrodynamical simulations exploring a wide range of parameter space show that the morphology of nuclear spirals depends not only on the inner dynamics but on the global dynamics resulting from the global mass distribution of galaxies. Thus, the nuclear morphology can be a diagnostic tool for the inner dynamics of galaxies when the global mass distribution is taken into account.

An Approach to Framework of Dealing with Improving the Complexity and Uncertainty for Decommissioning Safety Assessment of a Nuclear Facility

  • Jeong, Kwan-Seong;Lee, Kune-Woo;Lim, Hyeon-Kyo
    • International Journal of Safety
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    • 제8권1호
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    • pp.24-31
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    • 2009
  • An effective assessment for decommissioning safety of nuclear facilities requires basic knowledge about possible risks, characteristics of potential hazards, and comprehensive understanding of the associated cause-effect relationships within a decommissioning for nuclear facility. This paper proposes an approach to develop the hierarchical structure and hazards of dealing with improving the complexity and uncertainty for decommissioning safety assessment of nuclear facilities and the resolutions are proposed to improve the complexity and uncertainty for decommissioning safety assessment of nuclear facilities. These resolutions can provide a comprehensive view of the risks in the decommissioning activities of a nuclear facility.

AHP를 이용한 수출유망 원자력 기술 분야 선정 (Application of AHP to the Selection of Exportable Nuclear Technologies)

  • 이덕주;황주호;김상국;박광헌;강진수
    • 기술혁신연구
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    • 제12권1호
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    • pp.271-285
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    • 2004
  • The purpose of this paper is an application of AHP in the problem of exportable nuclear technology selection based on data gathered from nuclear experts. In this paper, the decision criteria for evaluating export competitiveness of nuclear technologies are identified and the hierarchical structure of decision making process is developed systematically. Subsequently the values of weights for relative importance among decision criteria are derived using AHP methodology, and the score of importance of nuclear technologies with respect to each criterion is evaluated. Finally the score indicating exportability of each nuclear technology is quantified in order to prioritize then. We discuss implications of our results with a viewpoint of national nuclear technology policy.

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Effect of Activation Time on the Nuclear Remodeling and In Vitro Development of Nuclear Transfer Embryos Derived from Bovine Somatic Cells

  • Choi, J. Y.;J. W. Cho;D. J. Kwon;Park, C. K.;B. K. Yang;Kim, C. I.;H. T. Cheong
    • 한국동물번식학회:학술대회논문집
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    • 한국동물번식학회 2002년도 춘계학술발표대회 발표논문초록집
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    • pp.6-6
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    • 2002
  • This study was conducted to investigate the effect of recipient activation time on the nuclear remodeling, chromatin structure, pronuclear formation and in vitro development of bovine nuclear transfer embryos derived from adult ear skin cells. Somatic cells were transferred to enucleated oocytes after quiescent treatments by serum starvation or culture to confluency. Nuclear transfer embryos were activated with a combination of Ca/sup 2+/-ionophore and cycloheximide at 1, 1.5, 2, 2.5, 3, and 5 h after electrofusion. (omitted)

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원전사고 평가를 위한 원전 사건유형분석 시스템(ETAS) 개발 (Development of the Event Type Analysis System (ETAS) for the Accident Evaluation in Nuclear Power Plants)

  • 최영환;김영미
    • 한국압력기기공학회 논문집
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    • 제5권2호
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    • pp.35-39
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    • 2009
  • In this study, Event Type Analysis System (ETAS) is developed for the accident evaluation in nuclear power plant. The ETAS system can be used in supporting regulator and/or operator under event situation in nuclear power plants. The ETAS system can categorize the all transient events to 3 categories such as Down-2000, Down-2173, and Slow Fluctuation. We develop the program structure for ETAS system and web-based ETAS system. The ETAS system will be used as sub module of Knowledge-Based Event Evaluation Network (K-EvENT) which is developing for the against the accident in nuclear power plants.

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