• Title/Summary/Keyword: Feedwater temperature

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Errors in One-Dimensional Heat Transfer Analysis in a Hollow Cylinder Feedwater Pipe (속이 빈 원관에서 1차원적인 열전달 해석의 오차)

  • Gang, Hyeong-Seok
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.20 no.2
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    • pp.689-696
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    • 1996
  • A comparison is made of the heat loss from a hollow cylinder, computed using an one-dimensional analytic method and a two-dimensional separation of variables scheme. For a two-dimensional analysis, the temperature of the inner surface as a boundary condition can be varied along the length of the cylinder by varing the temperature variation factor, b. Comparisons of the heat loss from the hollow cylinder using these two methods are given as a function of non-dimensional cylinder length, the ratio of the outer radius to the inner radius, temperature variation factor and Biot number. The result shows that the value of the heat loss from the hollow cylinder obtained using the one-dimensional analytic method becomes close to the value given by the two-dimensional separation of variables scheme as the value of Biot number and the non-dimensional hollow cylinder length increase and as the ratio of the outer radius to the inner radius decreases.

Performance analysis of an organic Rankine cycle for ocean thermal energy conversion system according to the working fluid and the cycle (작동유체 및 사이클에 따른 해양온도차발전용 유기랭킨사이클의 성능분석)

  • Kim, Jun-Seong;Kim, Do-Yeop;Kim, You-Taek;Kang, Ho-Keun
    • Journal of Advanced Marine Engineering and Technology
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    • v.39 no.9
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    • pp.881-889
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    • 2015
  • Ocean thermal energy conversion is an organic Rankine cycle that generates power using the temperature difference between surface water and deep water. This study analyzes the thermodynamic efficiency of the cycle, which strongly depends on the working fluid and the cycle configuration. Cycles studied included the classical simple Rankine cycle, Rankine cycles with an open feedwater heater and an integrated regenerator, as well as the Kalina cycle. Nine kinds of simple refrigerants and three kinds of mixed refrigerants were investigated as the working fluids in this study. Pinch-point analysis that set a constant pinch-point temperature difference was applied in the performance analysis of the cycle. Results showed that thermodynamic efficiency was best when RE245fa2 was used as the working fluid with the simple Rankine cycle, the Rankine cycles with an open feedwater heater and an integrated regenerator, and when the mixing ratio of $NH_3/H_2O$ was 0.9:0.1 in the Kalina cycle. If the Rankine cycles with an open feedwater heater, an integrated regenerator, and the Kalina cycle were used for ocean thermal energy conversion, efficiency increases could be expected to be approximately 2.0%, 1.0%, and 10.0%, respectively, compared to the simple Rankine cycle.

Robust $H_{\infty}$ Controller Design for Steam Generator Water Level Control using Mixed $H_{\infty}$ Optimization Method (혼합 $H_{\infty}$ 최적화 기법을 이용한 견실 $H_{\infty}$ 증기발생기 수위제어기 설계)

  • 서성환;조희수;박홍배
    • Journal of Institute of Control, Robotics and Systems
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    • v.5 no.3
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    • pp.363-369
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    • 1999
  • In this paper, we design the robust $H_{\infty}$ controller for water level control of steam generator using a mixed $H_{\infty}$ optimization with model-matching method. Firstly we choose the desired model which has good disturbance rejection performance. Secondly we design a stabilizing controller to keep the model-matching error small and also provide sufficiently large stability margin against additive perturbations of the nominal plant. Simulation results show that proposed robust $H_{\infty}$ controller at specific power operation has satisfactory performances against the variations of load power, steam flow rate, primary circuit coolant temperature, and feedwater temperature. It can be also observed that the proposed robust $H_{\infty}$ controller exhibits better robust stability than conventional PI controller.

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Immune Based Intelligent Tuning of the 2-DOF PID Controller for Thermal Power Plant

  • Kim, Dong-Hwa
    • 제어로봇시스템학회:학술대회논문집
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    • 2002.10a
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    • pp.101.3-101
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    • 2002
  • Contents 1 Abstract- In the thermal power plant, there are six manipulated variables; main steam flow, feedwater flow, air flow, spray flow, fuel flow, and gas recirculation flow. Therefore, the thermal power plant control system is a multi-input and output system. In the control system, the main steam temperature typically is regulated by the fuel flow rate and the spray flow rate, and the reheater steam temperature is regulated by the gas recirculation flow rate. Up to the present time, the PID controller has been used to operate this system. This paper focuses on the characteristic comparison of the PID controller, the modified 2-DOF PID Controller on the DCS, in order to design an optimal...

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A study on Decomposition Characteristics of Hydrazine (하이드라진의 분해특성 연구)

  • Kim Sang Dae;Ahn Hyun Kyoung;Yoon Hyoung Jun;Rhee In Hyoung
    • Proceedings of the KAIS Fall Conference
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    • 2004.11a
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    • pp.255-258
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    • 2004
  • Hydrazine is a weak base and strong reducing agent in the aqueous solution and is primarily utilized as a high-energy rocket propellant and an oxygen scavenger in boiler or feedwater. The objective of this study was to investigate the physicochemical properties and reactions of hydrazine and the catalytic and thermal decomposition by the temperature change. Hydrazine was fast decomposed with the catalyst of lower activation energy and at the higher temperature.

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Analysis of Loss of Normal Feedwater Transient Using RBLAP5/MOD1/NSC; KNU1 Plant Simulation (RELAP5/MOD1/NSC를 이용한 원자력 1호기 주급수 상실 사고 해석)

  • Hho Jung Kim;Bub Dong Chung;Young Jin Lee;Jin Soo Kim
    • Nuclear Engineering and Technology
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    • v.18 no.1
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    • pp.9-16
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    • 1986
  • Simulation of the system thermal-hydraulic parameters was carried out following the KNUl (Korea Nuclear Unit-1) loss of normal feedwater transient sequence occurred on November 14, 1984. Results were compared with the plant transient data, and good agreements were obtained. Some deviations were found in the parameters such as the steam flowrate and the RCS (Reactor Coolant System) average temperature, around the time of reactor trip. It can be expected since the thermal-hydraulic parameters encounter rapid transitions due to the large reduction of the reactor thermal power in a short period of time and, thereby, the plant data involve transient uncertainties. The analysis was performed using the RELAP5/MOD1/NSC developed through some modifications of the interphase drag and the wall heat transfer modeling routines of the RELAP5/MOD1/CY018.

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Analysis on Hypothetical Multiple Events of mSGTR and SBO at CANDU-6 Plants Using MARS-KS Code (중수로 원전 가상의 mSGTR과 SBO 다중 사건에 대한 MARS-KS 코드 분석)

  • Seon Oh YU;Kyung Won LEE;Kyung Lok BAEK;Manwoong KIM
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.17 no.1
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    • pp.18-27
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    • 2021
  • This study aims to develop an improved evaluation technology for assessing CANDU-6 safety. For this purpose, the multiple steam generator tube rupture (mSGTR) followed by an unmitigated station blackout (SBO) in a CANDU-6 plant was selected as a hypothetical event scenario and the analysis model to evaluate the plant responses was envisioned into the MARS-KS input model. The model includes logic models for controlling the pressure and inventory of the primary heat transport system (PHTS) decreasing due to the u-tubes' rupture, as well as the main features of PHTS with a simplified model for the horizontal fuel channels, the secondary heat transport system including the shell side of steam generators, feedwater and main steam line, and moderator system. A steady state condition was successfully achieved to confirm the stable convergence of the key parameters. Until the turbine trip, the fuel channels were adequately cooled by forced circulation of coolant and supply of main feedwater. However, due to the continuous reduction of PHTS pressure and inventory, the reactor and turbine were shut down and the thermal-hydraulic behaviors between intact and broken loops got asymmetric. Furthermore, as the conditions of low-flow coolant and high void fraction in the broken loop persisted, leading to degradation of decay heat removal, it was evaluated that the peak cladding temperature (PCT) exceeded the limit criteria for ensuring nuclear fuel integrity. This study is expected to provide the technical bases to the accident management strategy for transient conditions with multiple events.

Development of Main Steam Line Break Mass and Energy Release Analysis with RETRAN-3D Code

  • Park, Young-Chan;Kim, Yoo
    • Journal of Energy Engineering
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    • v.12 no.2
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    • pp.93-100
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    • 2003
  • An estimation methodology of the mass and energy (M/E) release due to the main steam line break (MSLB) has been developed with the RETRAN-3D code. In the case of equipment qualification (EQ), the over-estimated temperature would exceed the design limits of some cables or valves. In order to have a more flexible EQ profiles from the MSLB M/E release, the methodology with the best-estimated code was used. The major conditions affecting the MSLB M/E were found to be the initial SG level, heat transfer between primary and secondary sides, power level, operable protection system, main or auxiliary feedwater availability, and break conditions. The RETRAN-3D models were developed for the Kori unit 1 (KRN-1) which is typical two loop Westinghouse (WH) designed plant. Particularly, a detailed model of the steam generators was developed to estimate a more realistic two-phase heat transfer effect of the steam flow. After the modeling, the methodology has been developed through the sensitivity analyses. The M/E release data generated from the analyses have been used as the input to the inside containment pressure and temperature (P/T) analysis. According to the results at the point of view containment P/T, the Kori unit 1 can have more margin of 5∼15 ㎪ in pressure and 8∼15$^{\circ}C$ in temperature.

A Study on Vibration Control for Reheater Attemperator Piping in Power Plant (재열기 온도조절 급수배관의 진동저감방안 연구)

  • Jeon, Chang-Bin
    • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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    • 2007.11a
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    • pp.1-5
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    • 2007
  • A majority of piping vibration problems are induced by internal fluid pulsation; turbulent flow, vortex shedding at internal discontinuities, and pressure pulsation at equipment nozzles. The pulsation at the pressure sources resonates acoustically with the piping and the amplified pressure pulsation can generate shell mode vibration in the piping. Reheater attemperator piping supplies water from feedwater pump to reheater attemperator to control the boiler temperature. In normal operating condition, the high frequency shell mode vibration occurred in the piping with the high level of sound(105 ${\sim}$ 117 dB). The vibration sources are pressure pulsation in the pump nozzle and the frequencies are related to the blade passing frequencies. The objects of this paper are to analyze the cause of the high frequency vibration and to establish corrective actions.

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A Study on Improvement of PWR Steam Generator Water Level Control at Low Power Operation (저출력시 원전 증기발생기 수위제어 개선 연구)

  • Yun, Jae-Hee;Han, Jai-Bok;Joon Lyou
    • Nuclear Engineering and Technology
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    • v.26 no.3
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    • pp.420-424
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    • 1994
  • This paper presents an improved water level control scheme for Pressurized Water Reactor(PWR) Steam Generator(S/G) at the low power operation and transient states. To reduce fluctuations of the water level by the swell and shrink phenomena, the scheme adds feedforward terms considering S/G pressure and the feedwater temperature into the conventional proportional-integral feedback controller. The simulation results using the Compact Nuclear Simulator show that smaller level errors and much faster settling time than those of the conventional scheme can be obtained. The proposed algorithm is easily implementable and has a potential for the real applications.

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