• Title/Summary/Keyword: Main Steam

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A Study on the Vacuum System for High Efficiency Marine Steam Turbine System (대형 터어빈계통의 고효율 배압시스템 개발에 관한 연구(I))

  • 김경근;윤석환;김용모;김종헌;김철환
    • Journal of Advanced Marine Engineering and Technology
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    • v.18 no.4
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    • pp.13-24
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    • 1994
  • The demand of clean energy, like liquefied gas(LNG), increase suddenly because it generates few polluting substances when burned and from the point of view with caloric value it generates ralatively less $CO_2$ gas than the other energy sources. LNG transpotion method of our country is marine transportion by ships because the LNG producing district is far away from Korea. Main engines for most LNG ships are steam turbines, and the efficiency of steam turbine is influenced by the degree of vacuum of main steam condenser. This paper introduce the design method of the vacuum system for high efficiency marine steam turbine. Especially, it is developed the CAD program for the large steam condenser and steam ejector. Also, it is designed the pilot plant including high pressure boiler for the performance test and maked a part of this plant.

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EFFECTS OF AN ORIFICE-TYPE FLOW RESTRICTOR ON THE TRANSIENT THERMAL-HYDRAULIC RESPONSE OF THE SECONDARY SIDE OF A PWR STEAM GENERATOR TO A MAIN STEAM LINE BREAK (가압경수로 주증기관 파단시 증기발생기 2차측 과도 열수력 응답에 미치는 오리피스형 유량제한기의 영향)

  • Jo, J.C.;Min, B.K.
    • Journal of computational fluids engineering
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    • v.20 no.3
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    • pp.87-93
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    • 2015
  • In this study, a numerical analysis was performed to simulate the thermal-hydraulic response of the secondary side of a steam generator(SG) model equipped with an orifice-type SG outlet flow restrictor to a main steam line break(MSLB) at a pressurized water reactor(PWR) plant. The SG analysis model includes the SG upper steam space and the part of the main steam pipe between the SG outlet and the broken pipe end. By comparing the numerical calculation results for the present SG model to those obtained for a simple SG model having no flow restrictor, the effects of the flow restrictor on the thermal-hydraulic response of SG to the MSLB were investigated.

A Study on the Steam Hammering Characteristics by Sudden Closure of Main Stop Valve in the Main Steam Piping System of a Power Plant (화력발전소 주증기배관에서 밸브 차단에 따른 수증기 충격 특성에 관한 연구)

  • Ha, Ji-Soo;Lee, Boo-Youn
    • Journal of the Korean Institute of Gas
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    • v.17 no.2
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    • pp.70-77
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    • 2013
  • The present study has been carried out to analyze the effect of steam hammering on the steam piping system including the final superheater, the high pressure turbine, check valve and the first reheater by sudden stoping of main stop valve in a power plant. For the present steam hammering analysis, the well known Flowmaster software has been used to model the steam piping system and the time dependent characteristics of pressure and steam mass flow rate has been conducted. Using the result of the unsteady pressure and steam mass flow rate, the forces acting on the elbows in the piping system has been derived. From the present analysis, it has been elucidated that the elbow just before the main stop valve and the elbow near the connection pipe between bypass pipe and check valve had the largest force among the elbows in the steam piping system. The structural safety diagnostics study on the elbow and the supporting structures of the steam piping system of a power plant will be conducted in the future by the present results of the forces acting on the elbow.

Immune Based 2-DOF PID Controller Design for Complex Process Control

  • Kim, Dong-Hwa
    • 제어로봇시스템학회:학술대회논문집
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    • 2002.10a
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    • pp.70.2-70
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    • 2002
  • In the thermal power plant, it is difficult to maintain strict control of the steam temperature in order to avoid thermal stress, because of variation of the heating value according to the fuel source, the time delay of changes in main steam temperature versus changes in fuel flow rate, difficulty of control on the main steam temperature control and the reheater steam temperature control system owing to the dynamic response characteristics of changes in steam temperature and the reheater steam temperature, fluctuation of inner fluid water and steam flow rates widely during load-following operation. Up to the present time, the PID controller has been used to operate this system...

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Intelligent Tuning of the Two Degrees-of-Freedom Proportional-Integral-Derivative Controller On the Distributed Control System for Steam Temperature Control of Thermal Power Plant

  • Dong Hwa Kim;Won Pyo Hong;Seung Hack Lee
    • KIEE International Transaction on Systems and Control
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    • v.2D no.2
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    • pp.78-91
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    • 2002
  • In the thermal power plant, there are six manipulated variables: main steam flow, feedwater flow, fuel flow, air flow, spray flow, and gas recirculation flow. There are five controlled variables: generator output, main steam pressure, main steam temperature, exhaust gas density, and reheater steam temperature. Therefore, the thermal power plant control system is a multinput and output system. In the control system, the main steam temperature is typically regulated by the fuel flow rate and the spray flow rate, and the reheater steam temperature is regulated by the gas recirculation flow rate. However, strict control of the steam temperature must be maintained to avoid thermal stress. Maintaining the steam temperature can be difficult due to heating value variation to the fuel source, time delay changes in the main steam temperature versus changes in fuel flow rate, difficulty of control of the main steam temperature control and the reheater steam temperature control system owing to the dynamic response characteristics of changes in steam temperature and the reheater steam temperature, and the fluctuation of inner fluid water and steam flow rates during the load-following operation. Up to the present time, the Proportional-Integral-Derivative Controller has been used to operate this system. However, it is very difficult to achieve an optimal PID gain with no experience, since the gain of the PID controller has to be manually tuned by trial and error. This paper focuses on the characteristic comparison of the PID controller and the modified 2-DOF PID Controller (Two-Degrees-Freedom Proportional-Integral-Derivative) on the DCS (Distributed Control System). The method is to design an optimal controller that can be operated on the thermal generating plant in Seoul, Korea. The modified 2-DOF PID controller is designed to enable parameters to fit into the thermal plant during disturbances. To attain an optimal control method, transfer function and operating data from start-up, running, and stop procedures of the thermal plant have been acquired. Through this research, the stable range of a 2-DOF parameter for only this system could be found for the start-up procedure and this parameter could be used for the tuning problem. Also, this paper addressed whether an intelligent tuning method based on immune network algorithms can be used effectively in tuning these controllers.

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The Development of a Heat Balance Evaluation Program for the Main Steam Line of LNG Carrier (LNG선 주증기계통의 열평형산전용 전산프로그램 개발)

  • 최순호
    • Journal of Advanced Marine Engineering and Technology
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    • v.22 no.6
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    • pp.854-861
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    • 1998
  • The demand of LNG as a cheap and clean energy which does not cause an environmental problem has sharply been increased in Korea. In general LNG is stored in a cargo tank specially designed as a liquid state below $-162^{\circ}C$. The main engine of a LNG carrier is generally a steam boiler because LNG is a highly flammable fluid with the possibility of explosion. The main engine of a cargo ship has to be capable of the propulsion load and various auxiliary loads for the safe navigation since it is the primary energy source. Therefore the evaluation of a main boiler's energy capacity is a key design point in the planning of LNG carrier's construction. This research is to develop the computational program for the analysis of steam boiler Heat balance for LNG carrier.

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A Study on the Application of Phased Array Ultrasonic Testing to Main Steam Line in Nuclear Power Plants (원전 주증기배관 웰더렛 용접부 위상배열초음파검사 적용연구)

  • Lee, Seung-Pyo;Kim, Jin-Hoi
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.7 no.3
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    • pp.40-47
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    • 2011
  • KSNPs(Korea Standard Nuclear Power Plant) have been applied the break exclusion criteria to the high energy lines passing through containment penetration area to ensure that piping failures would not cause the loss of containment isolation function, and to reduce the resulting dynamic effects. Systems with the criteria are the Main Steam system, Feed Water system, Steam Generator Blowdown system, and Chemical & Volume Control system. In accordance with FSAR(Final Safety Analysis Report), a 100% volumetric examination by augmented in-service inspection of all pipe welds appled the break exclusion criteria is required for the break exclusion application piping. However, it is difficult to fully satisfy the requirements of inspection because 12", 8" and 6" weldolet weldments of Main Steam pipe line have complex structural shapes. To resolve the difficulty on the application of conventional UT(Ultrasonic Testing) technique, realistic mock-ups and UT calibration blocks were made. Simulations of conventional UT were performed utilizing CIVA, a commercial NDE(Nondestructive Examination) simulation software. Phased array UT experiments were performed through mock-up including artificial notch type flaws. A phased array UT technique is finally developed to improve the reliability of ultrasonic test at main steam line pipe to 12", 8" and 6" branch connection weld.

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

  • Yoon, Byung Sik;Moon, Gyoon Young;Kim, Yong Sik
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.11 no.1
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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.

Identification of Noise Source from Main Steam Line in Power Plant (발전소 주증기 배관 소음 발생 원인 규명)

  • Sohn, M.S.;Lee, J.S.;Lee, S.K.;Lee, W.R.;Lee, S.K.
    • Journal of Power System Engineering
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    • v.7 no.3
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    • pp.23-28
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    • 2003
  • In heavy nuclear power plant, high energy through main steam line is provided to turbine that generate the electric power. Since plant had generated power, high noise has been occurred. Noise make equipments and work environment worse. For finding out the location and the cause of making noise, noise was measured along main steam line at open/close test of Main Steam Isolation Valve (MSIV hereafter). As the result, it was identified that the vortex shedding in the cavity of MSIV is main noise source. The profile change of MSIV seat ring was proposed as the method of noise reduction. After filletting MSIV seat ring, the noise level reduced $10{\sim}20dB$ compared before the change of profile.

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STEAM on the Viewpoint of Didactics of Mathematics (수학교육학적 관점에서 바라본 STEAM 교육)

  • Seo, Dong Yeop
    • Journal of Educational Research in Mathematics
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    • v.24 no.3
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    • pp.429-442
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    • 2014
  • In this study we reviewed the backgrounds, main claims, and teaching and learning of STEAM education, and analysed STEAM education on the viewpoint of didactics of mathematics. The core competences of STEAM are creativity, communication, convergence, and caring. We found that the theoretical background of caring among these competences is relatively very weak, and the main principles for teaching and learing are mainly included the theories of didactics of mathematics and of creativity. We need to approach very carefully and progressively to creativity education through STEAM, and also need to study on the background of the mathematical creativity.

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