• Title/Summary/Keyword: 에너지 기여도 평가

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Evaluation of Energy Consumption of HVAC System for Air Filter Pressure Difference Change in Commercial Buildings (공조설비의 필터차압 변화에 따른 에너지 소비성능 평가)

  • Won Keun-Ho;Kwak Ro-Yeul;Huh Jung-ho
    • Korean Journal of Air-Conditioning and Refrigeration Engineering
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    • v.16 no.12
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    • pp.1227-1233
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    • 2004
  • Air handling unit (AHU)'s air filter pressure difference is important for energy consumption and indoor air quality. Both energy Performance data and air filter differential pressure of AHU in real office buildings were monitored and analyzed to investigate quantitatively energy impact as dust buildup level on air filter grows. We also modeled and simulated CAV system using HVACSIM+ program to examine the energy effect of dust buildup on filters. Through analysis of time series pressure drop data, the filter pressure difference rate has been increased due to cumulative supply air flow rate increase. As filter pressure drop increased to 1 inch water column, it is found that the supply air flow rate was decreased by 10%, the chilled water flow rate was increased by 5.9% and the pump energy consumption was increased to 5.9%.

Hydrogen Industry Cycle Infrastructure Safety Analysis (수소산업 전주기 인프라시설 안전성 분석)

  • WOOIL PARK;SEULKI CHOI;INWOO LEE;SEUNGKYU KANG
    • Journal of Hydrogen and New Energy
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    • v.33 no.6
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    • pp.795-802
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    • 2022
  • Korea is showing its appearance as a leading country in the hydrogen economy by establishing policies for revitalizing the hydrogen economy and enacting the 「Hydrogen Economy Promotion and Hydrogen Safety Management Act」 for the first time in the world. In addition, domestic hydrogen facilities are using hydrogen energy safely through world-class safety management compared to overseas advanced countries. However, in order to enhance the safety of the rapidly diversifying hydrogen industry and rapid technology development, such as the introduction of liquefied hydrogen, some institutional improvements are needed. In this regard, this paper intends to analyze the results of safety inspections on 13 representative facilities and prepare safety improvement plans to establish preemptive safety measures.

Combustion Reactivity Assessments of Oils Used for the Cold Start-Up Operation of Large Scale Boiler (대용량 보일러의 냉간기동용 액체 연료에 대한 연소 반응성 평가)

  • LEE, JANG HO;PARK, HO YOUNG
    • Journal of Hydrogen and New Energy
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    • v.33 no.1
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    • pp.77-84
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    • 2022
  • The experimental work has been carried out for the study of pyrolysis of oil samples used in industrial and utility boilers in Korea. For five oil samples, the characteristics of pyrolysis have been investigated with a thermogravimetric analyzer (TGA), and their kinetic parameters were obtained and compared each other. The rate order of pyrolysis rate for five oils were as follows: by-product fuel oil, pyrolysis oil, diesel, a heavy oil and refined oil. The pyrolysis of refined oil has been successfully described by the three step, first order reaction model while the single step reaction model has been used for other oils. For the reaction temperature over 550 K, the reactivity of refined oil was very poor compared with other oils.

Development of Dual-mode Signal Processing Module for Multi-slit Prompt-gamma Camera (다중 슬릿 즉발감마선 카메라를 위한 이중모드 신호처리 모듈 개발)

  • Park, Jong Hoon;Lee, Han Rim;Kim, Sung Hun;Kim, Chan Hyeong;Shin, Dong Ho;Lee, Se Byeong;Jeong, Jonh Hwi
    • Progress in Medical Physics
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    • v.27 no.1
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    • pp.37-45
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    • 2016
  • In proton therapy, in vivo proton beam range verification is very important to deliver conformal dose to the target volume and minimize unnecessary dose to normal tissue. For this purpose, a multi-slit prompt-gamma camera module made of 24 scintillation detectors and 24-channel signal processing system is under development. In the present study, we have developed and tested a dual-mode signal processing system, which can operate in the energy calibration mode and the fast data acquisition mode, to process the signals from the 24 scintillation detectors. As a result of performance test, using the energy calibration mode, we were able to perform energy calibration for the 24 scintillation detectors at the same time and determine the discrimination levels for the detector channels. Further, using the fast data acquisition mode, we were able to measure a prompt-gamma distribution induced by a 45 MeV proton beam. The measured prompt gamma distribution was found similar to the proton dose distribution at the distal fall-off region, and the estimated beam range was $17.13{\pm}0.76mm$, which is close to the proton beam range of 16.15 mm measured by an EBT film.

Pilot-scale Study for Pulse Power Pretreatment of Waste Activated Sludge (Pulse Power를 이용한 폐활성슬러지 전처리의 파이럿 규모 연구)

  • Yoo, Hee Chan;Hong, Seung Mo;Choi, Han Na
    • Journal of the Korea Organic Resources Recycling Association
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    • v.13 no.3
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    • pp.71-81
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    • 2005
  • Anaerobic digestion is employed worldwide as the oldest and most important process for sludge stabilization. An additional advantage is the production of methane during anaerobic digestion. However, the waste activated sludge(WAS) has poor anaerobic degradability and less gas production due to the cell wall of bio-solid. In order to improve and enhance stabilization and dewatering of the WAS, a number of pretreatment processes have been developed and investigated. In this research, a pilot-scale study of pulse power pretreatment was performed to improve anaerobic degradability and dewaterability of the WAS. A pilot plant was designed and operated based on a previous laboratory study. Change of the sludge characteristics by pulse power pretreatment was estimated to assess the increasing soluble organics. The increased soluble organics could be used as a good substrate in the anaerobic digesion process. Gas production and methane potential of the anaerobic digestion were estimated as the parameters of anaerobic degradability. For evaluation of the dewaterability of pretreated WAS, capillary suction time(CST) and specific resistance were measured. The efficiency of energy recovery was also estimated by calculating energy balance.

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Comparison of Domestic and Foreign Design Guides of Rockfall Protection Barriers (낙석방지 울타리에 대한 국내.외 설계 지침 비교)

  • Kim, Dong Seong;Kim, Kee Dong;Ko, Man Gi;Kim, Kyoung Ju
    • 한국방재학회:학술대회논문집
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    • 2011.02a
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    • pp.183-183
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    • 2011
  • 전 국토의 65%가 산악지형으로 이루어져 있는 우리나라는 도로개설 및 산업기지 건설, 대규모 주택단지 개발 등으로 자연사면을 변형시키는 규모나 빈도가 증가하고 있고, 최근에는 기상이변에 의한 집중호우가 빈번히 발생하여 절토사면에서 낙석이 발생할 위험이 점점 높아지고 있는 실정이다. 낙석방지를 위한 대책공법으로는 낙석방지 망, 낙석방지 울타리 등이 있으며 이중에서 낙석방지 울타리는 국내의 국도 낙석방지 대책공법 중 70% 이상을 차지하고 있다. 그러나 국내 설계지침에는 낙석방지 울타리에 대한 다양한 성능등급과 성능평가를 위한 표준화된 시험방법이 제시되어 있지 않아 현장여건을 고려하여 적절한 낙석방지 울타리를 선정하고 낙석방지 울타리들의 성능을 비교검토하기에 어려움이 있다. 유럽의 경우 유럽연합 출범이후 낙석방지 시설에 대한 통합기준의 필요성이 대두되어 유럽 여러 나라의 성능평가 방법과 스위스의 설계지침을 고려하여 2008년에 유럽 통합 지침인 ETAG 27을 제정하였다. ETAG 27에는 낙석방지 울타리의 성능등급이 100kJ~4,500kJ이상 9등급으로 분류되어 있고 성능등급 별로 Service Energy Level과 Maximum Energy Level에 대하여 실물시험을 통한 성능평가 시험과 구성요소에 대한 검증시험을 수행하도록 되어있다. 실물시험은 낙석에너지의 산정과 낙석질량의 타격위치를 정확하게 결정할 수 있는 방법을 이용하여 수행토록 규정되어 있다. 미국의 경우에는 주별로 상이한 설계기준으로 인하여 발생하는 문제를 해소하기 위하여 2003년에 스위스의 설계지침을 준용하여 통합기준인 NCHRP Report 20-07을 결정하였다. NCHRP Report 20-07에는 낙석방지 울타리의 성능등급이 100kJ~5,000kJ까지 9등급으로 분류되어 있고 성능등급 별 낙석질량이 규정되어 있으며 등급별 낙석에너지의 50%와 100%에 대하여 실물시험을 통한 성능평가 시험을 수행하도록 되어 있다. 실물시험은 낙석에너지의 산정과 낙석질량의 타격위치를 정확하게 결정할 수 있는 방법을 이용하여 수행토록 규정되어 있다. 낙석방지 울타리에 대한 국내 설계지침과 유럽과 미국의 설계지침을 비교분석하고 국내에서 수행된 실물실험을 통한 성능평가 연구결과를 검토하였다. 또한 구성요소의 역학적 특성변화가 전체 시스템의 성능에 미치는 영향을 조사하기 위해서 국내 설계 지침에 제시된 낙석방지 울타리에 대하여 컴퓨터 시뮬레이션을 이용한 성능평가를 수행하였다. 이러한 연구결과에 근거하여 국내 설계지침은 현장여건에 따라 적절한 낙석방지 울타리를 선정할 수 있도록 다양한 성능등급을 규정하고, 낙석방지 울타리의 성능을 합리적으로 비교검토 할 수 있게 하는 표준화 성능평가 시험방법과 평가기준을 정립하며, 구성요소의 품질에 대한 신뢰성을 확인하는 구성요소의 검증시험을 포함하는 방향으로 개선될 필요가 있는 것으로 조사되었다.

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Assessment of Effective Doses in the Radiation Field of Contaminated Ground Surface by Monte Carlo Simulation (몬테칼로 시뮬레이션에 의한 지표면 오염 방사선장에서의 유효선량 평가)

  • Chang, Jai-Kwon;Lee, Jai-Ki;Chang, Si-Young
    • Journal of Radiation Protection and Research
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    • v.24 no.4
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    • pp.205-213
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    • 1999
  • Effective dose conversion coefficients from unit activity radionuclides contaminated on the ground surface were calculated by using MCNP4A rode and male/female anthropomorphic phantoms. The simulation calculations were made for 19 energy points in the range of 40 keV to 10 MeV. The effective doses E resulting from unit source intensity for different energy were compared to the effective dose equivalent $H_E$ of previous studies. Our E values are lower by 30% at low energy than the $H_E$ values given in the Federal Guidance Report of USEPA. The effective dose response functions derived by polynomial fitting of the energy-effective dose relationship are as follows: $f({\varepsilon})[fSv\;m^2]=\;0.0634\;+\;0.727{\varepsilon}-0.0520{\varepsilon}^2+0.00247{\varepsilon}^3,\;where\;{\varepsilon}$ is the gamma energy in MeV. Using the response function and the radionuclide decay data given in ICRP 38, the effective dose conversion coefficients for unit activity contamination on the ground surface were calculated with addition of the skin dose contribution of beta particles determined by use of the DOSEFACTOR code. The conversion coefficients for 90 important radionuclides were evaluated and tabulated. Comparison with the existing data showed that a significant underestimates could be resulted when the old conversion coefficients were used, especially for the nuclides emitting low energy photons or high energy beta particles.

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Neutron Capture Resonance Energy Identification of Indium by Time-of-Flight Method (중성자 비행시간법을 이용한 인듐의 공명에너지 동정에 관한 연구)

  • Lee, Sam-Yol
    • Journal of the Korean Society of Radiology
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    • v.6 no.5
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    • pp.403-408
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    • 2012
  • Prompt gamma ray from the natural Indium sample was measured by using an assembly of BGO($Bi_4Ge_3O_{12}$) scintillation detectors in the neutron energy region from 1 to 300 eV. The assembly was composed of pieces of BGO. The spectrometer was composed geometrically as total energy absorption detector. 46-MeV electron linear accelerator which is located at Research Reactor Institute, Kyoto University used for neutron sources from photonuclear reaction. The measurement of the neutron capture resonances was performed to below neutron energy 1 keV, because of strong X-ray effect from photonuclear reaction in Ta target and short distance from the target to an assembly of detector. The distance of neutron flight path is $12.7{\pm}0.02m$. The large neutron capture resonances were measured from 1 to 400 eV. The energy in the capture resonance was compared with the evaluated values. The large resonances were seen in the present measurement. General agreement can be seen between the present measurement and the previous evaluated data in relevant energy region. In the present study, we measured the continues resonance structure above 1 keV neutron energy region. 91.49 eV new neutron capture resonance was found in present measurement.

An Evaluation of Heating Performance of the Heat Pump System Using Wasted Heat from Thermal Effluent for Greenhouse Facilities in Jeju (발전소 온배수 폐열을 이용한 제주 시설온실 냉난방용 열펌프 시스템의 난방성능 평가)

  • Moon, Sungbu;Hyun, Myung-Taek;Heo, Jaehyeok;Lee, Dong-Won;Lee, Yeon-Gun
    • Journal of Energy Engineering
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    • v.28 no.1
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    • pp.22-29
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    • 2019
  • A heat pump system using wasted heat from thermal effluent to supply the heating energy can reduce energy consumption and emissions of greenhouse gases by greenhouse facilities nearby. The Jeju National University consortium constructed a heat pump system using the thermal effluent from the Jeju thermal power plant of KOMIPO to provide with cool or hot water to greenhouse facilities located 3 km from the power station. In this paper, the system configuration of the heat pump system was summarized, and the results of operations for demonstration of a heating performance carried out during the winter season in 2018 were investigated. The preoperational tests proved that the water temperature drop through the pipeline transporting extracted heat was less than $2^{\circ}C$. The COP (coefficient of performance) of the heat pump was higher than 4.0, and hot water with the maximum temperature of $50^{\circ}C$ could be supplied to greenhouse facilities by utilizing wasted heat from thermal effluent.

Characterization of Radiation Field in the Steam Generator Water Chambers and Effective Doses to the Workers (증기발생기 수실의 방사선장 특성 및 작업자 유효선량의 평가)

  • Lee, Choon-Sik;Lee, Jai-Ki
    • Journal of Radiation Protection and Research
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    • v.24 no.4
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    • pp.215-223
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    • 1999
  • Characteristics of radiation field in the steam generator(S/G) water chamber of a PWR were investigated and the anticipated effective dose rates to the worker in the S/G chamber were evaluated by Monte Carlo simulation. The results of crud analysis in the S/G of the Kori nuclear power plant unit 1 were adopted for the source term. The MCNP4A code was used with the MIRD type anthropomorphic sex-specific mathematical phantoms for the calculation of effective doses. The radiation field intensity is dominated by downward rays, from the U-tube region, having approximate cosine distribution with respect to the polar angle. The effective dose rates to adults of nominal body size and of small body size(The phantom for a 15 year-old person was applied for this purpose) appeared to be 36.22 and 37.06 $mSvh^{-1}$) respectively, which implies that the body size effect is negligible. Meanwhile, the equivalent dose rates at three representative positions corresponding to head, chest and lower abdomen of the phantom, calculated using the estimated exposure rates, the energy spectrum and the conversion coefficients given in ICRU47, were 118, 71 and 57 $mSvh^{-1}$, respectively. This implies that the deep dose equivalent or the effective dose obtained from the personal dosimeter reading would be the over-estimate the effective dose by about two times. This justifies, with possible under- or over- response of the dosimeters to radiation of slant incidence, necessity of very careful planning and interpretation for the dosimetry of workers exposed to a non-regular radiation field of high intensity.

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