• 제목/요약/키워드: Waste factor

검색결과 545건 처리시간 0.031초

폐주물사를 혼입한 콘크리트의 최적배합설계를 위한 기초적 연구 (Preliminary Study for Optimum Mix Design of Concrete Incorporating Waste Foundry Sand)

  • 박제선;김태경
    • 산업기술연구
    • /
    • 제16권
    • /
    • pp.25-30
    • /
    • 1996
  • The waste foundry sand might be recycled in concrete, resulting in energy saving and environmental protection. An half Factorial Experiments were performed with the variables of W/C ratio, S/A, Sand/Waste foundry sand ratio and Slump as a preliminary study for optimum mix design of concrete. The results show that then W/C ratio is the most important factor to the concrete strength. The substitute of waste foundry sand up to 30% has little influence, saying that it can substitute the fine aggregate without damaging the concrete properties.

  • PDF

폐주물사를 혼입한 콘크리트의 최적 배합설계를 위한 기초적 연구 (Preliminary Study for Optimum Mix Design of Concrete Incorporation Waste Foundary Sand)

  • 백민경;이주형;김태경;윤경구;박제선
    • 한국콘크리트학회:학술대회논문집
    • /
    • 한국콘크리트학회 1996년도 가을 학술발표회 논문집
    • /
    • pp.58-63
    • /
    • 1996
  • The waste foundry sand might be recycled in concrete, resulting in energy saving and environmental protection. An half Factorial Exprements were performed with the variables of W/C ratio, S/A, Sand/Waste foundry sand ratio and Slump as a preliminary study for optimum mix design of concrete. The results show that the W/C ratio is the most important factor to the concrete strength. The substitute of waste foundry sand up to 30% has little influence, saying that it can substitute the fine aggregate without damaging the concrete properties.

  • PDF

핀 형상에 따른 폐열회수용 핀-튜브 열교환기의 성능분석 (Performance Analysis of Fin-Tube Heat Exchangers with Various Fin Shapes for Waste Gas Heat Recovery)

  • 맹재훈;구병수;전용두;이금배
    • 설비공학논문집
    • /
    • 제23권9호
    • /
    • pp.627-632
    • /
    • 2011
  • As an innovative effort to secure economically viable heat recovery system, various fin shapes for industrial fin-tube heat exchangers have been studied for better performance. In this study, the waste gas heat recovery from four different fin shapes was experimentally performed for heat transfer rate and pressure drop. According to the tested results, the twist and wavy shape fins of rectangular type show the superior performance in terms of Goodness factor and jH/f factor ratio, whereas the circular spiral fin shows the inferior values. Experimental results shows good comparison with the numerical results with a slight discrepancy of 5%, which is quite resonable.

냉동컨테이너에서의 HFC-134a 탈루배출 특성에 대한 연구 (Fugitive Emission Characteristics of HFC-134a from Reefer Container)

  • 김의건;김승도;이영표;변석호;김혜림
    • 한국대기환경학회지
    • /
    • 제30권2호
    • /
    • pp.110-118
    • /
    • 2014
  • This paper addresses the fugitive emission factors of Reefer Container at use-phase and disposal-phase. The residual quantities and operation time of thirty nine Container were weighed, using a commercial recover of refrigerants to determine the emission factors at the use-phase. The emission factor at the disposal-phase, refrigerant is accomplished has not recycled, the residual rate was assumed that the emission factor. The average residual rate of thirty nine Container is determined to be $70.8{\pm}4.0%$. The emission factor at the use-phase is estimated to be $4.9{\pm}0.9%/yr$ in the case of using average age of 8.1 years and the average residual rate determined here. We estimate 162.7 g/yr for the average emission quantity of refrigerant per operating Container, while 2038.1 g for that per waste Container. Since the chemical compositions of refrigerant of waste Container were the same as those of new refrigerant, it is expected that the refrigerant recovered from waste Container can be reused for refrigerant.

Acceptable Decontamination Factor for Near-Surface Disposal of PEACER Wastes

  • Kim, Sung-Il;Lee, Kun-Jai
    • 한국방사성폐기물학회:학술대회논문집
    • /
    • 한국방사성폐기물학회 2005년도 Proceedings of The 6th korea-china joint workshop on nuclear waste management
    • /
    • pp.280-289
    • /
    • 2005
  • A pyrochemical process has been introduced and utilized so that the transmutation of spent PWR fuel in PEACER can produce mainly low and intermediate level waste for near surface disposal. Major radioactive nuclides from PEACER pyroprocessing are composed of TRU and LLFP. In this study, the requirement for the final waste from PEACER is evaluated based on the methodology for establishment of waste acceptance criteria. Also, sensitivity analysis for several input parameters is conducted in order to determine acceptable decontamination factor (DF) and LLFP removal efficiency and to find out input parameter that extremely have an effect on DE As a result of the study, LLFP removal efficiency, especially Sr-90 and Tc-99, is proved to be a major nuclide which contributes to annual dose by human intrusion scenario rather than TRU DF. More than $98.5\%$ of LLFP have to be removed to meet below dose constraint within the DF more than 5.0E+03. Besides, because of the relative short half-life of Sr-90, the increasing of the institutional control period is recommended for most important input parameter to determine DF.

  • PDF

외열킬른형 열분해용융시설의 N2O 배출계수 개발 (The Development of N2O Emission Factor at Killn Type Pyrolysis Melting Facility)

  • 윤현기;이대겸;조창상;강성민;윤영중;전영재;전의찬
    • 한국기후변화학회지
    • /
    • 제8권3호
    • /
    • pp.231-237
    • /
    • 2017
  • In this study, the $N_2O$ emission factor of the facility was developed by measuring the kiln type pyrolysis melting facility. This used PAS (Photoacoustic Spectroscopy) method and measured the $N_2O$ emission concentration. From March 2016 to April 2016, it was measured over a total of two times and $N_2O$ concentrations were measured continuously for 24 hours using a 24 hour continuous measuring instrument (LSE-4405). The measured $N_2O$ emission concentration of the pyrolysis melting facility was 0.263 ppm on average and the emission concentration distribution in the range of 0.013~0.733 ppm was obtained. Therefore, the $N_2O$ emission factor of the kiln-type pyrolysis melting facility was estimated to be $0.829gN_2O/ton$-Waste. As a result of comparing the $N_2O$ emission factor of the thermal kiln type pyrolysis melting facility and the previous study, previous studies were about 18 times higher. It is estimated that this is due to the difference of furnace temperature, oxygen concentration and denitrification facilities. It is considered that the study of the emission factor of pyrolysis melting facility is an important factor in improving the credibility of greenhouse gas inventory in waste incineration sector.

유도무기 비행시험 업무 개선을 위한 낭비요인과 우선순위 분석 연구 (A Study on Waste Factors and Improvement Priorities of Missile Flight Test Works)

  • 안장근;김의환
    • 한국군사과학기술학회지
    • /
    • 제21권4호
    • /
    • pp.541-550
    • /
    • 2018
  • The works of preparing for missile flight test are becoming more complicated. To reduce the amount of waste time along with the complexity of the task, systematic analysis of waste factors should be performed before performing process improvement. The waste factors for missile flight test are first defined using lean-based waste factors. The improvement priorities for the defined waste factors are surveyed. For reliable analysis, AHP is used in questionnaire analysis instead of the existing method with large error. Then weighting and priority for waste factors for level 1 and Level 2 are suggested. Through AHP, we could derive reliable improvement priorities for waste factors. It is analyzed that the biggest cause of waste factors is waiting time and identified as the first item to be considered when establishing improvement plan. In addition, suggestions for improvement measures of waste factors are presented through brainstorming method. Reliable results will be an important factor in process redesign for missile flight test works.

폐김치냉장고에서의 HFC-134a 탈루배출 특성에 대한 연구 (Fugitive Emission Characteristics of HFC-134a from Waste Kimchi Refrigerator)

  • 김의건;김승도;이영표
    • 한국대기환경학회지
    • /
    • 제30권1호
    • /
    • pp.59-67
    • /
    • 2014
  • In 1995 Kimchi refrigerator was developed at first, and has used HFC-134a as refrigerant. Kimchi refrigerator has been made 1,044,694 on the basis of 2010, disposed about 160,000 per year. Although mobile air conditioning, commercial refrigerator, general refrigerator is regarded as a major source of HFC-134a, little information is available for its emission characteristics of HFC-134a. This paper addresses the fugitive emission factors of Kimchi refrigerator at use-phase and disposal-phase. The residual quantities of Korean-made fifty three waste Kimchi refrigerators were weighed using a commercial recover of refrigerants to determine the emission factors at the disposal-phase. On the other hand, the emission factors at use-phase were estimated from the residual quantities and operating times. The average residual rate of forty three scarp Kimchi refrigerators is determined to be $74.6{\pm}5.2%$. The emission factor at the use-phase is estimated to be $3.5{\pm}0.8%/yr$ as a result of using average age of 11.7 years and the average residual rate determined here. The emission factor at the disposal-phase is determined to be 31.3% after adopting 58% of the recycling rate of refrigerant reported by Recycling Center. We estimate 3.1 g/yr for the average emission quantity of HFC-134a per operating refrigerator, while 22.5 g for that per waste Kimchi refrigerator. Since the chemical compositions of refrigerant of waste Kimchi refrigerator were the same as those of new refrigerant, it is expected that the HFC-134a recovered from waste Kimchi refrigerator can be reused for refrigerant.

인공신경망 이론을 이용한 척도인자 결정방법의 향상방안에 관한 연구 (A Study on the Improvement of Scaling Factor Determination Using Artificial Neural Network)

  • Sang-Chul Lee;Ki-Ha Hwang;Sang-Hee Kang;Kun-Jai Lee
    • 방사성폐기물학회지
    • /
    • 제2권1호
    • /
    • pp.35-40
    • /
    • 2004
  • Final disposal of radioactive waste generated from Nuclear Power Plant (NPP) requires the detailed information about the characteristics and the quantities of radionuclides in waste package. Most of these radionuclides are difficult to measure and expensive to assay. Thus it is suggested to the indirect method by which the concentration of the Difficult-to-Measure (DTM) nuclide is estimated using the correlations of concentration - it is called the scaling factor - between Easy-to-Measure (Key) nuclides and DTM nuclides with the measured concentration of the Key nuclide. In general, the scaling factor is determined by the log mean average (LMA) method and the regression method. However, these methods are inadequate to apply to fission product nuclides and some activation product nuclides such as 14$^{C}$ and 90$^{Sr}$ . In this study, the artificial neural network (ANN) method is suggested to improve the conventional SF determination methods - the LMA method and the regression method. The root mean squared errors (RMSE) of the ANN models are compared with those of the conventional SF determination models for 14$^{C}$ and 90$^{Sr}$ in two parts divided by a training part and a validation part. The SF determination models are arranged in the order of RMSEs as the following order: ANN model

  • PDF