• Title/Summary/Keyword: Energy plant

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Physiological Activities Exerted by Various Growth Regulators, Ca and K ion on Elongation of Soybean Hypocotyl Segments (대두유축신장에 미치는 각종생장 조절물질과 석탄 및 가리의 생리적작용에 대하여)

  • 곽병화
    • Journal of Plant Biology
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    • v.11 no.1
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    • pp.22-26
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    • 1968
  • Hypocotyl segments of shade-grown soybean sprouts(var. Kumdo) were floated in solutions of various substances at physiological levels and grown for either 24 hours at 28$^{\circ}C$ or 72 hours at $25^{\circ}C$. Increased length of the segments beyond 20mm (the original length) was obtained as a measure of the present studies. At the room temperature, Ca and DNP strongly inhibited elongation of the hypocotyl segments, whereas K, IAA, GA and EDTA in general promoted it. There were, however, no such differences in the effects at relatiely low temperature. This indicated that the elongation process not only involves stretching of wall materials, but also does synthesis of the materials. Ca was found to be antagonistic to the promotive action of GA in the elongation, and the IAA action involves metabolic energy. EDTA seemed to act as a widely known chelator removing Ca already existed in the hypocotyl tissue, thus shwoed a promotion in the elongation.

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The Study of Improvement in Reactor Thermal Power Measurement Method using KALMAN FILTER (KALMAN FILTER를 이용한 원자로 열출력측정 방법개선에 관한 고찰)

  • 정남교
    • Journal of the Korean Professional Engineers Association
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    • v.30 no.5
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    • pp.82-95
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    • 1997
  • A Study of Improvement in Reactor Thermal Power Measurement Method using Kalman Filter. The objectives of the safety analysis of nuclear power plants are to maintain the surface temperature of fuel and fuel cladding within limit value in case of Loss of Coolant accident (LOCA) so that it ensures the safety and reliability of nuclear power plants. The new technique evaluating the reactor power and improvement of existing plant system increase the safety margin of nuclear power plant operation, and accordingly, economic effect will be anticipated. Hereby, 1 would like to introduce reactor power measurement method using Kalman filter that enables to calculate the reactor power more precisely combining the parameters, for example, turbine output as the 1 st stage pressure of high pressure turbine, and reactor power using energy equilibrium relation. It is expected that the new technique will enhance the accuracy of measurement of reactor power and maintain the reliability of nuclear power operation by increasing operational safety margin, and gain the economic benefit

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Flow and Heat Transfer Analysis of Reactor Coolant Pump in Transient Conditions (원자로 냉각재 펌프의 과도 상태의 유동 및 열전달 해석 연구)

  • Hur, N.;Kim, S.;Yoo, K.-P.;Kim, S. T.
    • 유체기계공업학회:학술대회논문집
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    • 1999.12a
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    • pp.245-251
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    • 1999
  • The structural analysis of a reactor coolant pump(RCP) of a nuclear power plant is very important for the safety assessment of the plant. Accurate boundary conditions for the heat transfer coefficient are required for reliable thermal stress analysis of the pump casing, especially in transient operations of the pump since the coolant properties are largely dependent on operational conditions. In the present study, a 3D mixed flow type coolant pump was modeled from the RCP drawings and analyzed in the steady state and number of transient flow conditions by using a commercial code STAR-CD. From the result of the computation, it is seem that the average heat transfer coefficients for the cases considered are found to be the suggested values of the manufacturer, Westinghouse Energy System. The unevenness in local heat transfer coefficients, however, is found to be considerable so that the use of average heat transfer coefficients in all boundaries might not give reliable thermal stresses.

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Development of Noise Source Detection System using Array Microphone in Power Plant Equipment (배열형 음향센서를 이용한 발전설비 소음원 탐지시스템 개발)

  • Sohn, Seok-Man;Kim, Dong-Hwan;Lee, Wook-Ryun;Koo, Jae-Raeyang;Hong, Jin-Pyo
    • KEPCO Journal on Electric Power and Energy
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    • v.1 no.1
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    • pp.99-104
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    • 2015
  • In this study, it has been initiated to investigate the specific abnormal vibration signal that has been captured in the power equipment. Array Microphone can be used in order to detect the direction and the position of the noise source. It is possible to track the abnormal mechanical noise in the power plant by utilizing the program and the microphone array system developed from this research. Array microphone system can be operated as a constant monitoring system.

A Study on the Harmonics and Flicker Measurements and Analysis of the Grid Connected Photovoltaic Power System (전력계통 연계형 태양광 발전시스템의 고조파 및 플리커의 측정 및 분석에 관한 연구)

  • Kim, Kyung-Chul;Kim, Yong-Kwan
    • Journal of the Korean Institute of Illuminating and Electrical Installation Engineers
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    • v.26 no.5
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    • pp.48-57
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    • 2012
  • This paper analyzes the characteristic of gird connected photovoltaic power generation system which is available to connect the utility. Renewable energy photovoltaic power system has been linked to the system to analyze the impact of photovoltaic system. It is measured that power data for the Grid connected photovoltaic power plant with instantaneous measuring and 3-sec measuring for 7 days. Harmonic field measurements have shown that the harmonic contents of a waveform varies with time. A cumulative probability approach is the most commonly used method to solve time varying harmonics. So, it is used 50[%] cumulative probability approach. This paper provides an in depth analysis on power quality field measurement of the Grid connected photovoltaic power plant.

Output Characteristic Analysis of Small Hydropower Plant (소수력발전소의 출력특성 분석)

  • Park, Wan-Soon;Lee, Chul-Hyung
    • 한국신재생에너지학회:학술대회논문집
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    • 2006.06a
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    • pp.491-494
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    • 2006
  • The output performance characteristics for surveyed sites were analyzed, using developed model. It consists of two main parts, the deciding flow duration characteristic of river and performance prediction model to estimate the output characteristics of small hydropower plants. As a result, it was found that the flowrate concerning with 25% of time ratio on flow duration curve can be selected to design flowrate of small hydropower plants, and the output characteristics of small hydropower plants having overflow dam are different from large scale hydropower plants.

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Development of Dynamic Model of 680 MW Rated Steam Turbine and Verification and Validation of its Speed Controller (680 MW 증기터빈 동적모델 개발 및 속도제어기 검증)

  • Choi, Inkyu;Woo, Joohee;Son, Gihun
    • KEPCO Journal on Electric Power and Energy
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    • v.5 no.3
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    • pp.165-171
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    • 2019
  • The steam turbine used in nuclear power plant is modeled for the purpose of verification of control system rather than the operator education. The valves, reheater and generator are modeled also and integrated into the simulator. After that, the operation data and the designed data such as heat balance diagram are utilized to identify the model parameters. It was evident that model outputs of developed simulator are very close to the measured operating ones. The simulator within dynamic model was used to verify and validate the whole control system together with field instruments. And the target plant has been operating long time.

Analysis of Corrosion Behavior of KOFA Zircaloy-4 Cladding

  • Lee, Chan-Bock;Kim, Ki-Hang
    • Nuclear Engineering and Technology
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    • v.30 no.2
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    • pp.173-179
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    • 1998
  • The corrosion behavior of KOFA cladding which is a standard Zircaloy-4 manufactured by Westinghouse Specialty Metal Plant according to the Siemens/KWU's HCW (Highly Cold Worked) standard Zircaloy-4 specification was analyzed using the oxide measurement data of KOFA fuel irradiated in Kori-2 nuclear power plant. Analysis of the measured KOFA cladding oxidation showed that oxidation of KOFA cladding was lower than the design prediction based upon Siemens/KWU's HCW standard Zircaloy-4 cladding. Although the measured fuel rods have relatively low burnup and oxidation and the amount of the measured data are small, analysis of manufacturing and in-reactor operation conditions of KOFA cladding indicates that the differences in the manufacturing processes and chemical composition of the Siemens/KWU's HCW (Highly Cold Worked) standard Zircaloy-4 and KOFA cladding may have somewhat contributed to lower corrosion of KOFA cladding than the expected.

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A REAL-TIME REMOTE SENSING AND DATA ACQUISITION SYSTEM FOR A NUCLEAR POWER PLANT

  • Kim, Ki-Ho;Hieu, Bui Van;Beak, Seung-Hyun;Choi, Seung-Hwan;Son, Tae-Ha;Kim, Jung-Kuk;Han, Seung-Chul;Jeong, Tai-Kyeong
    • Nuclear Engineering and Technology
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    • v.43 no.2
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    • pp.99-104
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    • 2011
  • A Structure Health Monitoring (SHM) system needs a real-time remote data acquisition system to monitor the status of a structure from anywhere via Internet access. In this paper, we present a data acquisition system that monitors up to 40 Fiber Bragg Grating Sensors remotely in real-time. Using a TCP/IP protocol, users can access information gathered by the sensors from anywhere. An experiment in laboratory conditions has been done to prove the feasibility of our proposed system, which is built in special-purpose monitoring system.

OPTIMIZATION OF THE TEST INTERVALS OF A NUCLEAR SAFETY SYSTEM BY GENETIC ALGORITHMS, SOLUTION CLUSTERING AND FUZZY PREFERENCE ASSIGNMENT

  • Zio, E.;Bazzo, R.
    • Nuclear Engineering and Technology
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    • v.42 no.4
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    • pp.414-425
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    • 2010
  • In this paper, a procedure is developed for identifying a number of representative solutions manageable for decision-making in a multiobjective optimization problem concerning the test intervals of the components of a safety system of a nuclear power plant. Pareto Front solutions are identified by a genetic algorithm and then clustered by subtractive clustering into "families". On the basis of the decision maker's preferences, each family is then synthetically represented by a "head of the family" solution. This is done by introducing a scoring system that ranks the solutions with respect to the different objectives: a fuzzy preference assignment is employed to this purpose. Level Diagrams are then used to represent, analyze and interpret the Pareto Fronts reduced to the head-of-the-family solutions.