• Title/Summary/Keyword: Internal Power

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STEADY-STATE OPTIMIZATION OF AN INTERNAL COMBUSTION ENGINE FOR HYBRID ELECTRIC VEHICLES

  • Wang, F.;Zhang, T.;Yang, L.;Zhuo, B.
    • International Journal of Automotive Technology
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    • v.8 no.3
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    • pp.361-373
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    • 2007
  • In previous work, an approach based on maximizing the efficiency of an internal combustion engine while ignoring the power conversion efficiency of other powertrain components, such as the electric motor and power battery or ultracapacitor, was implemented in the steady-state optimization of an internal combustion engine for hybrid electric vehicles. In this paper, a novel control algorithm was developed and successfully justified as the basis for maximal power conversion efficiency of overall powertrain components. Results indicated that fuel economy improvement by 3.9% compared with the conventional control algorithm under China urban transient-state driving-cycle conditions. In addition, using the view of the novel control algorithm, maximal power generation of the electric motor can be chosen.

Analysis of the Likelihood of Internal Radiation Exposure When Decommissioning a Nuclear Power Plant in Korea

  • Jiung Kim;Tae Young Kong;Seongjun Kim;Jinho Son;Changju Song;Jaeok Park;Seungho Jo;Hee Geun Kim
    • Journal of Radiation Industry
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    • v.18 no.2
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    • pp.141-145
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    • 2024
  • In Publication No. 66 of the International Commission on Radiological Protection, an activity median aerodynamic diameter (AMAD) of 5 ㎛ is considered in internal exposure dose assessment owing to inhalation of radionuclides in a workplace. However, analysis of aerosols generated during dismantling experiments, such as in the oxy-cutting of a reactor vessel conducted in Korea, revealed that the radioactive aerosols have AMAD ranging from 0.024 to 0.064 ㎛. Such extremely fine aerosols can induce internal exposure if inhaled. In particular, alpha radionuclides in aerosols can lead to significantly higher levels of radiation exposure than beta and gamma radionuclides, thus highlighting the need to establish appropriate internal exposure radiation protection programs and monitoring systems that specifically address alpha radionuclides when decommissioning nuclear power plants in Korea.

Performance Analysis of R-1270(Propylene) Refrigeration System Using Internal Heat Exchanger (내부 열교환기를 이용한 R-1270용 냉동시스템의 성능 분석)

  • Ku, Hak-Keun
    • Journal of Power System Engineering
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    • v.18 no.4
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    • pp.36-42
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    • 2014
  • This paper considers the influence of internal heat exchangers on the efficiency of a refrigerating system using R-1270. These internal heat exchangers(liquid-gas or suction-line heat exchangers) can, in some cases, yield improved system performance while in other cases they degrade system performance. A steady state mathematical model is used to analysis the performance characteristics of refrigeration system with internal heat exchanger. The influence of operating conditions, such as the mass flowrate of R-1270, inner diameter tube and length of internal heat exchanger, to optimal dimensions of the heat exchanger is also analyzed. The main results were summarized as follows : the mass flowrate of R-1270, inner diameter tube and length of internal heat exchanger, and effectiveness have the influences on the cooling capacity, compressor work and RCI(Relative Capacity Index) of this system. With a thorough grasp of it is possible to design the R-1270 compression refrigeration cycle using internal heat exchanger.

A Signal Anti-reduction System for Power Line Communication

  • Ko Jong-Sun;Kim Hyun-Sik;Hong Soon-Chan
    • Journal of Power Electronics
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    • v.4 no.4
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    • pp.256-260
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    • 2004
  • A new communication system is suggested using a single-phase full-bridge inverter with high efficiency ferrite core for power line communication (PLC). The conventional system has a decreasing signal voltage problem due to internal resistance. The proposed system has almost zero internal impedance and replaces a linear amplifier.

Systematic Approach of Internal Parameters for Equivalent Electrical-Circuit Modeling(EECM) of a Li4Ti5O12(LTO) cell (Li4Ti5O12(LTO) 배터리 등가회로 모델링을 위한 내부 파라미터 체계적 해석)

  • Lee, Pyeong-Yeon;Yoon, Chang-O;Park, Jin-Hyeong;Kim, Jonghoon
    • The Transactions of the Korean Institute of Power Electronics
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    • v.23 no.3
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    • pp.174-181
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    • 2018
  • This study introduces a systematic approach to selecting the internal parameters applied to the equivalent electrical-circuit model (EECM) of a lithium titanium oxide ($Li_4Ti_5O_{12}$; LTO) rechargeable cell. Based on the dynamic characteristic of the cell, a simplified EECM consisting of an open-circuit voltage (OCV), an ohmic resistance, and an RC ladder is fabricated. To select the internal parameters of a simplified EECM, experiments on discharge capacity, OCV, and discharge/charge resistances are performed using hybrid pulse power characterization and direct current internal resistance (DCIR) measurements over the full state-of-charge (SOC) range. The experimental results of the LTO rechargeable cell highlight the importance of correct selection of internal parameters that can reduce EECM errors. This study clearly provides experimental procedures, internal parameters results, and EECM guidelines for adaptive control-based SOC estimation for LTO rechargeable cells.

Advanced Protective Relaying Algorithm by Flux-Differential Current Slope Characteristic for Power Transformer (전력용 변압기용 자속-차전류 기울기 특성에 의한 개선된 보호계전 알고리즘)

  • 박철원;신명철
    • The Transactions of the Korean Institute of Electrical Engineers A
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    • v.53 no.7
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    • pp.382-388
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    • 2004
  • The most widely used primary protection for the internal fault detection of power transformers is current percentage differential relaying(PDR). However, the harmonic components could be decreased by magnetizing inrush when there have been changes to the material of iron core or its design methodology. The higher the capacitance of high voltage status and underground distribution, the more differential current includes the second harmonic component during occurrence of an internal fault. Therefore, the conventional harmonic restraint methods need modification. This paper proposes an advanced protective relaying algorithm by fluxt-differential current slope characteristic and trend of voltage and differential current. To evaluate the performance of proposed algorithm, we have made comparative studies of PDR fuzzy relaying, and DWT relaying. The paper is constructed power system model including power transformer, utilizing the WatATP99, and data collection is made through simulation of various internal faults and inrush. As the results of test. the new proposed algorithm was proven to be faster and more reliable.

Study on the Real-Time Leak Monitoring Technique for Power Plant Valves (발전용 밸브누설 실시간 감시기술 연구)

  • Lee, S.G.
    • Journal of Power System Engineering
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    • v.11 no.1
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    • pp.39-44
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    • 2007
  • The purpose of this study is to verify availability of the acoustic emission in-situ monitoring method to the internal leak and operating conditions of the major valves at nuclear power plants. In this study, acoustic emission tests are performed when the pressurized temperature water and steam flowed through glove valve(main steam dump valve) and check valve(main steam outlet pump check valve) on the normal size of 12 and 18". The valve internal leak monitoring system for practical field was designed. The acoustic emission method was applied to the valves at the site, and the background noise was measured for the abnormal plant condition. To improve the reliability, a judgment of leak on the system was used various factors which are AE parameters, trend analysis, frequency analysis, voltage analysis and amplitude analysis of acoustic signal emitted from the valve operating condition internal leak.

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Study on Evaluation of the Leak Rate for Steam Valve in Power Plant (발전용 증기밸브 누설량 평가에 관한 연구)

  • Lee, S.G.;Park, J.H.;Yoo, G.B.
    • Journal of Power System Engineering
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    • v.11 no.1
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    • pp.45-50
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    • 2007
  • Acoustic emission technology is applied to diagnosis the internal leak and operating conditions of the major valves at nuclear power plants. The purpose of this study is to verify availability of the acoustic emission as in-situ diagnosis method. In this study, acoustic emission tests are performed when the pressurized high temperature steam flowed through gate valve(1st stage reheater valve) and glove valve(main steam dump valve) on the normal size of 4 and 8". The valve internal leak diagnosis system for practical field was designed. The acoustic emission method was applied to the valves at the site, and the background noise was measured for the abnormal plant condition. To improve the reliability, a judgment of leak on the system was used various factors which are AE parameters, trend analysis, signal level analysis and RMS(root mean square) analysis of acoustic signal emitted from the valve operating condition internal leak.

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Preliminary Study on the Internal Dosimetry Program for Carbon-14 at Korean CANDU Reactors (중수로원전에서 발생하는 $^{14}C$에 대한 내부피폭 선량평가 프로그램에 관한 예비 조사)

  • Kong T.Y.;Kim H.C.;Park G.;Hang D.W.;Lee G.J.;Lee S.K.;Park S.C.
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2005.11a
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    • pp.317-320
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    • 2005
  • More strict radioactive regulations are applied to Korean nuclear power plants (NPPs) since ICRP-60 recommendation for radiation protection and has been enforced since 2003. In particular. carbon-14 and tritium concentrations are significantly higher at CANDU reactors compared to PWR reactors and this increases the risk of internal radiation exposure to workers at CANDU NPPs. Thus, it is necessary to estimate the exact amount of internal radiation exposure to workers fur radiological protection at CANDU reactors. In this paper, the current dosimetry method for carbon-14 is analyzed for the establishment of internal dosimetry for carbon-14 at domestic NPPs.

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DEVELOPMENT OF THE DUAL COUNTING AND INTERNAL DOSE ASSESSMENT METHOD FOR CARBON-14 AT NUCLEAR POWER PLANTS

  • Kim, Hee-Geun;Kong, Tae-Young;Han, Sang-Jun;Lee, Goung-Jin
    • Journal of Radiation Protection and Research
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    • v.34 no.2
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    • pp.55-64
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    • 2009
  • In a pressurized heavy water reactor (PHWR), radiation workers who have access to radiation controlled areas submit their urine samples to health physicists periodically; internal radiation exposure is evaluated by the monitoring of these urine samples. Internal radiation exposure at PHWRs accounts for approximately 20 $\sim$ 40% of total radiation exposure; most internal radiation exposure is attributed to tritium. Carbon-14 is not a dominant nuclide in the radiation exposure of workers, but it is one potential nuclide to be necessarily monitored. Carbon-14 is a low energy beta emitter and passes relatively easily into the body of workers by inhalation because its dominant chemical form is radioactive carbon dioxide ($^{14}CO_2$). Most inhaled carbon-14 is rapidly exhaled from the worker's body, but a small amount of carbon-14 remains inside the body and is excreted by urine. In this study, a method for dual analysis of tritium and carbon-14 in urine samples of workers at nuclear power plants is developed and a method for internal dose assessment using its excretion rate result is established. As a result of the developed dual analysis of tritium and carbon-14 in urine samples of radiation workers who entered the high radiation field area at a PHWR, it was found that internal exposure to carbon-14 is unlikely to occur. In addition, through the urine counting results of radiation workers who participated in the open process of steam generators, it was found that the likelihood of internal exposure to either tritium or carbon-14 is extremely low at pressurized water reactors (PWRs).