• Title/Summary/Keyword: Nuclear Turbine

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The development of turbine valve actuator efficiency analysis system for the standard power plants (표준형 발전소용 터빈 밸브 작동기 성능 분석 시스템 개발)

  • Roh, J.H.;Kim, S.H.;Lee, D.I.;Yang, C.K.;Shin, Y.Y.;Jung, J.W.
    • Proceedings of the KIEE Conference
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    • 2002.11c
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    • pp.537-541
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    • 2002
  • This paper is about the development of the turbine valve actuator efficiency analysis system for the standard power plants. We developed hydraulic power unit and turbine valve actuator controller. We designed control algorithm for turbine valve actuator, implemented and verified it at the industrial plants.

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Methodology for Centrifugal Stress Estimation Model Development of Large Steam Turbine Blades (스팀 터빈 블레이드 원심응력 추정을 위한 전산해석 연구)

  • Lee, Byounghak;Park, Jongho
    • The KSFM Journal of Fluid Machinery
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    • v.16 no.6
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    • pp.26-31
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    • 2013
  • Last blades of low-pressure turbine in nuclear power plant are the highly damaged part and always suffered from different types of loadings leading to various stress components, stresses due to centrifugal force and steam flow loading. Especially, centrifugal stress generated by turbine rotation is one of the main problems and more significant than other stresses as they have the greatest effect on total stress. Therefore, this study was performed to obtain the important information for estimation model development of the blade centrifugal stress level and distribution.

A SMALL MODULAR REACTOR DESIGN FOR MULTIPLE ENERGY APPLICATIONS: HTR50S

  • Yan, X.;Tachibana, Y.;Ohashi, H.;Sato, H.;Tazawa, Y.;Kunitomi, K.
    • Nuclear Engineering and Technology
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    • v.45 no.3
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    • pp.401-414
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    • 2013
  • HTR50S is a small modular reactor system based on HTGR. It is designed for a triad of applications to be implemented in successive stages. In the first stage, a base plant for heat and power is constructed of the fuel proven in JAEA's $950^{\circ}C$, 30MWt test reactor HTTR and a conventional steam turbine to minimize development risk. While the outlet temperature is lowered to $750^{\circ}C$ for the steam turbine, thermal power is raised to 50MWt by enabling 40% greater power density in 20% taller core than the HTTR. However the fuel temperature limit and reactor pressure vessel diameter are kept. In second stage, a new fuel that is currently under development at JAEA will allow the core outlet temperature to be raised to $900^{\circ}C$ for the purpose of demonstrating more efficient gas turbine power generation and high temperature heat supply. The third stage adds a demonstration of nuclear-heated hydrogen production by a thermochemical process. A licensing approach to coupling high temperature industrial process to nuclear reactor will be developed. The low initial risk and the high longer-term potential for performance expansion attract development of the HTR50S as a multipurpose industrial or distributed energy source.

Development of Special Steels for Turbine Blade of Nuclear Power Plant (원자력 터빈 블레이드용 특수강 개발)

  • Im, Cha-Yong;Kim, Seong-Jun
    • 연구논문집
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    • s.24
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    • pp.119-128
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    • 1994
  • A special steels have been developed for the possible applications of turbine blade in nuclear power plant. The compositions of developed alloy were selected by the reference of imported alloy. The various properties such as tensile property, impact energy, hardness, and microstructures were investigated. All the properties of optimum heat treated materials were satisfied with the present specifications of turbine blade materials in unclear power plant. Furthermore, FATT(Fracture appearance transition temperature), high temperature tensile properties, and transformation temperatures of developed alloy also have been studied.

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A Study on Non Destructive Evaluation of the Steam Turbine L-0 Blades

  • Mizanur, Rahman Md.;Rezk, Osama;Ouma, Victor Otieno;Vaysidin, Saidov;Gomaa, M. Abdullatif;Jung, JaeCheon;Lee, YongKwan
    • Journal of the Korean Society of Systems Engineering
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    • v.12 no.1
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    • pp.59-71
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    • 2016
  • The Nuclear and Fossil Steam Turbines record a considerable number of failures annually. Some of these failures reported are as result of blade failure. The failure of the L-0 blade in a Steam Turbine is one of the most reported blade failure in Nuclear and Fossil steam turbines. This paper seeks to identify the best Non Destructive Evaluation (NDE) method or methods to be used in the steam turbine L-0 blades inspection process. The development of systems engineering processes presents an opportunity to apply NDE inspection to the L-0 blades. This process apply computer modelling of the L-0 using ANSYS and by simulating the stresses experienced by the L-0 blade during operation it is possible to identify the most susceptible areas for crack formation and growth. The results from these models compared to industry data for validation. The analysis of these results used to predict the most probable failure location and failure modes. Therefore NDE inspection can be applied to these areas with greater degree of accuracy. This would be beneficial in the increasing the accuracy in the detection of cracks and hence save inspection time and the overall inspection cost. Furthermore, not only the location for crack formation and NDE inspection determined but also best the NDE inspection technique/techniques to be applied appropriately on the L-0 blade are prescribed.

Effect of Dissolved Oxygen on the Stress Cor rosion Cracking Behavior of 3.5NiCrMoV Steels in High Temperature Water

  • Lee, J.H.;Maeng, W.Y.;Kim, U.C.
    • Corrosion Science and Technology
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    • v.2 no.4
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    • pp.178-182
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    • 2003
  • Slow Strain Rate Tests (SSRT) were carried out to investigate the effect of environmental factors on the Stress Corrosion Cracking (SCC) susceptibility of 3.5NiCrMoV steels used in discs for Low-Pressure (LP) steam turbines in electric power generating plants. The influences of dissolved oxygen on the stress corrosion cracking of turbine steel were studied, For this purpose, specimens were strained at variously oxygenated conditions at $150^{\circ}C$ in pure water. When the specimen was strained with $1{\times}10^{-7}s^{-1}$ at $150^{\circ}C$ in pure water, increasing concentration of dissolved oxygen decreased the elongation and the UTS. The corrosion potential and the corrosion rare increased as the amounts of dissolved oxygen increased. The increase of the SCC susceptibility of the turbine steel in a highly dissolved oxygen environment is due to the non protectiveness of the oxide layer on the turbine steel surface and the increase of the corrosion current. These results clearly indicate that oxygen concentration increases Stress Corrosion Cracking susceptibility in turbine steel at $150^{\circ}C$.

A study on the dynamic characteristics of the secondary loop in nuclear power plant

  • Zhang, J.;Yin, S.S.;Chen, L.;Ma, Y.C.;Wang, M.J.;Fu, H.;Wu, Y.W.;Tian, W.X.;Qiu, S.Z.;Su, G.H.
    • Nuclear Engineering and Technology
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    • v.53 no.5
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    • pp.1436-1445
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    • 2021
  • To obtain the dynamic characteristics of reactor secondary circuit under transient conditions, the system analysis program was developed in this study, where dynamic models of secondary circuit were established. The heat transfer process and the mechanical energy transfer process are modularized. Models of main equipment were built, including main turbine, condenser, steam pipe and feedwater system. The established models were verified by design value. The simulation of the secondary circuit system was conducted based on the verified models. The system response and characteristics were investigated based on the parameter transients under emergency shutdown and overload. Various operating conditions like turbine emergency shutdown and overspeed, condenser high water level, ejector failures were studied. The secondary circuit system ensures sufficient design margin to withstand the pressure and flow fluctuations. The adjustment of exhaust valve group could maintain the system pressure within a safe range, at the expense of steam quality. The condenser could rapidly take out most heat to avoid overpressure.

Recent Trend to the Forging Technology of Power Plant Components and Status of Forging Company (발전용 소재 단조기술 및 국내 단조업계 동향)

  • Kim, J.T.;Chang, H.S.;Kim, D.K.;Kim, Y.D.;Kim, D.Y.
    • Proceedings of the Korean Society for Technology of Plasticity Conference
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    • 2007.05a
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    • pp.38-41
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    • 2007
  • The increase of $CO_2$ emission by increasing of fossil fuel usage has been understood a major cause of global warming. The supply of electric energy is heavily dependent on the massive thermal power and nuclear power plant before developing the renewable energy to supply the electric energy stably at a low price. The large and sound forged components of pressure vessel, turbine and generator are widely used in power plant such as wind power, hydroelectric power generation, nuclear power and thermal power plant. This paper is discussed the trend of manufacturing technology for pressure vessel and turbine to satisfy the required condition of utility company. It is also introduced a strategy of forging industry to cope with carbon tax.

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