• 제목/요약/키워드: National Major Facility

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수정된 Steiner Point를 이용한 Batcher Plant의 최적 위치 선정 (Optimal location of Batcher Plant using Modified Steiner point)

  • 하권열;이상중
    • 조명전기설비학회논문지
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    • 제29권10호
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    • pp.39-46
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    • 2015
  • REMICON(Ready Mixed Concrete), the most essential material of construction work, is produced from facility called "Batcher plant." In order to produce Remicon, Batcher Plant needs to be supplied with basic raw material such as ballast, sand, cement, admixture and water. In remicon industry, overland transport vehicles are used during the whole manufacturing process from producing to infilling at the construction site. Thus, the transportation cost sums up be to 20 percent of whole manufacturing cost and transport capacity and distance travelled have direct and major effect on manufacturing costs. This paper suggests a method to find optimal location of batcher plant using modified Steiner point, suggesting the most effective and flexible connection through among construction site, aggregate, cement and remicon producing plant. This paper also proposes reducing of transport cost at maximum 60% by calculation through optimized plant location. The modified Steiner point theory proposed in this paper also can be applied to optimal location of a $2^{ry}$ substation or MCC panel for minimizing of power loss, voltage drop, line distance and etc.

한강하구지역의 항만시설 개발방안 연구 (A Study on the Development Plan for the Port Facility in the Han River Estuary)

  • 최용석;최상희;양창호
    • 한국항해항만학회:학술대회논문집
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    • 한국항해항만학회 2006년도 춘계학술대회 및 창립 30주년 심포지엄(논문집)
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    • pp.153-162
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    • 2006
  • 본 연구의 목적은 남한과 북한간의 화물운송을 위한 해상운송과 항만서비스를 위한 협력적인 관리계획을 수립하고 한강하구와 서해접경지역에 해상운송과 항만개발의 번영을 신속히 실현하는 방안을 제공하는 것이다. 특히 해상평화공원을 둘러싼 환경을 보존하기 위한 노력을 개발계획에 반영하는 것이다. 본 연구의 취지는 한강하구지역의 번영은 보존을 병행한 해상운송과 항만서비스의 개발을 통해서 가능하다는 것을 보이는 것이다.

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Development of an evaluation method for nuclear fuel debris-filtering performance

  • Park, Joon-Kyoo;Lee, Seong-Ki;Kim, Jae-Hoon
    • Nuclear Engineering and Technology
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    • 제50권5호
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    • pp.738-744
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    • 2018
  • Fuel failure due to debris is a major cause of failure in pressurized water reactors. Fuel vendors have developed various filtering devices to reduce debris-induced failure and have evaluated filtering performance with their own test facilities and methods. Because of the different test facilities and methods, it is difficult to compare filtering performances objectively. This study presents an improved filtering test and an efficiency calculation method to fairly compare fuel-filtering efficiency regardless of the vendor's filtering features. To enhance the reliability of our evaluation, we established requirements for the test method and had a facility constructed according to the requirements. This article describes the debris specimens, the amount of debris, and the replicates for the proposed test method. A calculation method of comprehensive debris-filtering efficiency using a weighted mean is proposed. The test method was verified by repeated tests, and the tests were carried out using the PLUS7 and 17ACE7 test fuels to calculate the comprehensive debris-filtering efficiencies. The evaluation results revealed that the filtering performance of PLUS7 is better than that of 17ACE7. The proposed method can be used on any kind of debris-filtering devices and is appropriate for use as a standard.

Experiments and MAAP4 Assessment for Core Mixture Level Depletion After Safety Injection Failure During Long-Term Cooling of a Cold Leg LB-LOCA

  • Kim, Y. S.;B. U. Bae;Park, G. C.;K. Y. Sub;Lee, U. C .
    • Nuclear Engineering and Technology
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    • 제35권2호
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    • pp.91-107
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    • 2003
  • Since DBA(Design Basis Accidents) has been studied rather separately from SA(Severe Accidents) in the conventional nuclear reactor safety analysis, the thermal hydraulics during transition between DBA and SA has not been identified so much as each accident itself. Thus, in this study, the thermal hydraulic behavior from DBA to the commencement of SA has been experimentally and analytically investigated for the long-term cooling phase of LB-LOCA(Large-Break Loss-of-Coolant Accident). Experiments were conducted for both cases of the loop seal open and closed in an integral test loop, named as SNUF (Seoul National University Facility), which was scaled down to l/6.4 in length and 1/178 in area of the APR1400 (Advanced Power Reactor 1400MWe). The core mixture level was a main measured value since it took major role in the fuel heat-up rate, the location of fuel melting initiation and the channel blockage by melting material during SA. Experimental results were compared to MAAP4.03 to assess its model of calculating the core mixture level. MAAP4.03 overestimates the core two- phase mixture level because sweep-out and spill-over and the measures to simulate the status of loop seal are not included, which is against the conservatism. Thus, it is recommended that MAAP4.03 should be improved to simulate the thermal hydraulic phenomena, such as sweep-out, spill-over and the status of loop seal.

Uncertainty analyses of spent nuclear fuel decay heat calculations using SCALE modules

  • Shama, Ahmed;Rochman, Dimitri;Pudollek, Susanne;Caruso, Stefano;Pautz, Andreas
    • Nuclear Engineering and Technology
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    • 제53권9호
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    • pp.2816-2829
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    • 2021
  • Decay heat residuals of spent nuclear fuel (SNF), i.e., the differences between calculations and measurements, were obtained previously for various spent fuel assemblies (SFA) using the Polaris module of the SCALE code system. In this paper, we compare decay heat residuals to their uncertainties, focusing on four PWRs and four BWRs. Uncertainties in nuclear data and model inputs are propagated stochastically through calculations using the SCALE/Sampler super-sequence. Total uncertainties could not explain the residuals of two SFAs measured at GE-Morris. The combined z-scores for all SFAs measured at the Clab facility could explain the resulting deviations. Nuclear-data-related uncertainties contribute more in the high burnup SFAs. Design and operational uncertainties tend to contribute more to the total uncertainties. Assembly burnup is a relevant variable as it correlates significantly with the SNF decay heat. Additionally, burnup uncertainty is a major contributor to decay heat uncertainty, and assumptions relating to these uncertainties are crucial. Propagation of nuclear data and design and operational uncertainties shows that the analyzed assemblies respond similarly with high correlation. The calculated decay heats are highly correlated in the PWRs and BWRs, whereas lower correlations were observed between decay heats of SFAs that differ in their burnups.

Performing a multi-unit level-3 PSA with MACCS

  • Bixler, Nathan E.;Kim, Sung-yeop
    • Nuclear Engineering and Technology
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    • 제53권2호
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    • pp.386-392
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    • 2021
  • MACCS (MELCOR Accident Consequence Code System), WinMACCS, and MelMACCS now facilitate a multi-unit consequence analysis. MACCS evaluates the consequences of an atmospheric release of radioactive gases and aerosols into the atmosphere and is most commonly used to perform probabilistic safety assessments (PSAs) and related consequence analyses for nuclear power plants (NPPs). WinMACCS is a user-friendly preprocessor for MACCS. MelMACCS extracts source-term information from a MELCOR plot file. The current development can combine an arbitrary number of source terms, representing simultaneous releases from a multi-unit facility, into a single consequence analysis. The development supports different release signatures, fission product inventories, and accident initiation times for each unit. The treatment is completely general except that the model is currently limited to collocated units. A major practical consideration for performing a multi-unit PSA is that a comprehensive treatment for more than two units may involve an intractable number of combinations of source terms. This paper proposes and evaluates an approach for reducing the number of calculations to be tractable, even for sites with eight or ten units. The approximation error introduced by the approach is acceptable and is considerably less than other errors and uncertainties inherent in a Level 3 PSA.

Radiological Safety Assessment for a Near-Surface Disposal Facility Using RESRAD-ONSITE Code

  • Jang, Jiseon;Kim, Tae-Man;Cho, Chun-Hyung;Lee, Dae Sung
    • 방사성폐기물학회지
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    • 제19권1호
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    • pp.123-132
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    • 2021
  • Radiological impact analyses were carried out for a near-surface radioactive waste repository at Gyeongju in South Korea. The RESRAD-ONSITE code was applied for the estimation of maximum exposure doses by considering various exposure pathways based on a land area of 2,500 ㎡ with a 0.15 m thick contamination zone. Typical influencing input parameters such as shield depth, shield materials' density, and shield erosion rate were examined for a sensitivity analysis. Then both residential farmer and industrial worker scenarios were used for the estimation of maximum exposure doses depending on exposure duration. The radiation dose evaluation results showed that 60Co, 137Cs, and 63Ni were major contributors to the total exposure dose compared with other radionuclides. Furthermore, the total exposure dose from ingestion (plant, meat, and milk) of the contaminated plants was more significant than those assessed for inhalation, with maximum values of 5.5×10-4 mSv·yr-1 for the plant ingestion. Thus the results of this study can be applied for determining near-surface radioactive waste repository conditions and providing quantitative analysis methods using RESRAD-ONSITE code for the safety assessment of disposing radioactive materials including decommissioning wastes to protect human health and the environment.

농촌 생활서비스 시설 분포와 인구감소지역의 비교분석 (Comparative Analysis of Spatial Distribution of Rural Living Service Facilities and Depopulation Areas)

  • 최진아;김상범;김수연;조한솔
    • 한국농촌건축학회논문집
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    • 제24권4호
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    • pp.77-84
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    • 2022
  • The purpose of this study is to derive implications by comparing the spatial distribution of each service facility per unit population(1,000 people) with population decline areas. For this purpose, major concepts such as living infrastructure services, Spatial Distribution of Rural Living Service Facilities, areas of declining population, and regional extinction were reviewed and trends in prior research. Based on the literature review, 'Spatial Distribution of Rural Living Service Facilities' analysis criteria were set, and it was derived by 'the number of facilities per 1,000 population by township' using population data and rural space data. And the trend of each service sector was identified and implications were derived with 89 cities and counties in 'depopulation areas' suggested by the Ministry of Public Administration and Security. The derived implications are as follows. In the medical, leisure, and sports infrastructure sectors, 'rural areas with few service facilities per unit population' and 'depopulated areas' tended to coincide. In addition, the distribution characteristics of rural and urban areas differed by sector, which is judged to depend on the inclusion of rural facilities and population density.

낙동강 수계에서 제사방적제조 업체에 대한 공정별 원단위산정 및 분석 (Unit Mass Estimation and Analysis from Textile Spinning/Weaving Manufacturing Facility Nearby Nakdong River Basin)

  • 이홍신;손건태;구정은;콘분락사;이홍태;이승환
    • 상하수도학회지
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    • 제22권5호
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    • pp.541-550
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    • 2008
  • In this investigative study, the unit mass discharge for the major water quality parameters such as flowrate, SS, BOD, CODmn, CODcr, TN, TP from textile spinning/weaving industry nearby Nakdong river basin was estimated. To represent the respective industries, three companies from hundreds of textile spinning/weaving industries located in Nakdong river basin was carefully selected based on its manufacturing goods, flowrate and location for the estimation of unit mass discharge based on unit operation and process. There was a drastic decrease of unit mass discharge estimation between influents and effluents of water quality parameters, which represents the removal capacity of wastewater treatment plant. With the advent of new regulation on the imposed payment proportional to the total amount of pollutants discharge into the water body, the concept of cleaner production technology should be employed in the unit operation/process in wastewater treatment plant as well as textile manufacturing procedure to minimize the levy on the pollutants discharge. Unit mass discharge estimations of unit process (estimated in this study) in major water quality parameters (SS, BOD, COD, TN and TP) based on land were similar to those of composite process (estimated by National Institute of Environmental Research). But the unit mass discharge estimations of unit process in BOD and CODmn based on total sale were much higher than those of composite one while in SS, TN and TP similar to each other. For the detailed estimation of the imposed payment, unit mass estimation based on unit process should be further emphasized.

남산도시자연공원내 생물서식공간 조성에 관한 연구 (A Study of Creating a Biotope in Namsan Urban Natural Park)

  • 강현경;이수동
    • 한국환경복원기술학회지
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    • 제9권2호
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    • pp.45-58
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    • 2006
  • This study was aimed to propose the plan of creating a biotope reflecting an ecological education as well as its function as the habitats of amphibian in Namsan Urban Natural Park in Seoul. There were Cheonil mineral spring area which was located on the southern side of Namsan, wetlands which was already created on the east valley(800$m^2$) and a buffer area of the circumference(1,100$m^2$) as the biotope sites. Major fields of this study include a survey of the staus, a basic plan, a master plan; a survey of this site was focused on topography, water system, existing vegetation, wildbird, amphibian, trail; a detailed plan was focused on flow plan, planting plan, facility plan. Existing vegetation was classified into 8 types; Pinus densiflora forest, Pinus densiflora planted area, Prunus sargentii-Quercus spp. forest, Pinus rigida forest, Robinia pseudoacacia forest, artificial green space, wetlands, south beltway. There were Pinus densiflora planted area and Prunus sargentii-Quercus spp. forest as major vegetations of this site. 14 species and 33 individuals of wildbirds appeared, Rana temporaria ornativentris and Hynobius leechi were investigated in the wetlands.In particular, habitats of amphibian were divided eco-zone, buffer-zone and restore-zone, and habitats and facilities which would be suitable for the characteristics of each space were planned. As a result, environment elements of good habitats including spawn wetlands of amphibian, harbor of amphibian, water plant of wetland, wild shrubs forest, ecological landscape forest, wetland observation trail, fence of wetland protection and ramp by pebble and log were created at the site. The amphibian biotope of Namsan is rated high as an important space for conserving biodiversity. Accordingly, continuous monitoring of this biotope as a urban habitat is required as the environment changes.