• Title/Summary/Keyword: 중간저장시설

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Analysis on the Potentiality of Domestic Rainwater Harvesting in Metro Manila (마닐라 지역의 가정용 우수저류시설 잠재가용성 분석)

  • Felix, Micah Lourdes A.;Maniquiz, Marla C.;Seo, Sung-Ho;Kim, Lee-Hyung;Jeong, Sang-Man
    • Journal of Wetlands Research
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    • v.13 no.3
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    • pp.633-641
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    • 2011
  • The Philippines is known for its abundant water resources such as the rainfall, where it has a mean annual rainfall range from 965 to 4,100mm. Due to the rapid urbanization of the country, the population in Metro Manila has been continuously increasing hence, the demand for a potable water supply also increases. To mitigate the scarcity of potable water supply, utilization of the water resources should be practiced. Rainwater harvesting is one way to utilize the rainfall runoff. This study analyzedthe potentiality of the rainwater harvesting on residential areas in Metro Manila. A water balance method based spreadsheet was used with input parameters including daily rainfall, catchment area, runoff coefficient, population and the water demand. The efficiency of the domestic water tank was analyzedusing the three different climatic conditions (i.e., minimum, median andmaximum annual rainfalls) and three different types of toilets (i.e., inefficient, conventional and dual-flush toilets). Furthermore, the overflow volume was used to determine which size of rainwater storage was more appropriate for the study area. The results of the study showed that for the three types of rainfall years, only the conventional and dual-flush toilets were suitable for the utilization of rainwater harvesting. The utilization of the $60m^3$ storage tank was sufficient for supplying the demandsof the 90 houses only for a small period of time, 3 months. Based from this study, to fully sustain the long-term water demand of the houses, the enlargement of the tank size having a capacity of 1,100 to $2,500m^3$ is ideal.

A Study on Radiation Safety Evaluation for Spent Fuel Transportation Cask (사용후핵연료 운반용기 방사선적 안전성평가에 관한 연구)

  • Choi, Young-Hwan;Ko, Jae-Hun;Lee, Dong-Gyu;Jung, In-Su
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.17 no.4
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    • pp.375-387
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    • 2019
  • In this study, the radiation dose rates for the design basis fuel of 360 assemblies CANDU spent nuclear fuel transportation cask were evaluated, by measuring radiation source terms for the design basis fuel of a pressurized heavy water reactor. Additionally, radiological safety evaluation was carried out and the validity of the results was determined by radiological technical standards. To select the design basis fuel, which was the radiation source term for the spent fuel transportation cask, the design basis fuels from two spent fuel storage facilities were stored in a spent fuel transportation cask operating in Wolsung NPP. The design basis fuel for each transportation and storage system was based on the burnup of spent fuel, minimum cooling period, and time of transportation to the intermediate storage facility. A burnup of 7,800 MWD/MTU and a minimum cooling period of 6 years were set as the design basis fuel. The radiation source terms of the design basis fuel were evaluated using the ORIGEN-ARP computer module of SCALE computer code. The radiation shielding of the cask was evaluated using the MCNP6 computer code. In addition, the evaluation of the radiation dose rate outside the transport cask required by the technical standard was classified into normal and accident conditions. Thus, the maximum radiation dose rates calculated at the surface of the cask and at a point 2 m from the surface of the cask under normal transportation conditions were respectively 0.330 mSv·h-1 and 0.065 mSv·h-1. The maximum radiation dose rate 1 m from the surface of the cask under accident conditions was calculated as 0.321 mSv·h-1. Thus, it was confirmed that the spent fuel cask of the large capacity heavy water reactor had secured the radiation safety.

Management, Feeding Practices, Milk Yield and its Quality in Korean Dairy Farms: a Survey (낙농농가의 관리수준, 사양형태, 유생산성과 우유품질에 관한 조사)

  • 김현섭;이왕식;기광석;이현준;백광수;안병석;아주말 칸;김상범
    • Journal of Animal Science and Technology
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    • v.48 no.3
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    • pp.479-486
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    • 2006
  • The current study was conducted to examine the effect of feeding and management practices on milk quality and dairy farm productivity in Korea. Fifty dairy farms in Gyunggi (11), Gangwon (22), Chungnam (17) provinces were surveyed to collect data on the herd size, housing style, feeding management, waste disposal, milking practices and milk yield. Milk tank samples from all farms under study were also collected to enumerate its composition and quality parameters. Large dairy herds are equiped with better housing, milking and waste control facilities than medium and small dairy herds. Higher concentrate feeding to lactating cows was noticed in small dairy herds (47.51 %) than in medium (32.59 %) and large dairy herds (31.82 %). The decrease in concentrate feeding to lactating cows with increase in number of cows per farm resulted in a simultaneous increase in the use of imported forages. Bacterial count in milk was affected by housing and milking facilities at dairy farms. Higher bacterial counts (Coliform and E. coli) in milk were observed in cows housed in stanchion than those under free stall with saw dust bedding. The bacterial counts were higher with bucket milking system than with pipe-line and parlour systems. The increase in the number of dairy cows per farm and thus better management and milking facilities resulted in a reduction in somatic cell score. Milk yield (per cow) was higher in herds with less somatic cell score. Average milk protein concentration was between 2.89 to 2.98 % and milk urea nitrogen was between 21.81 to 23.31mg/ml on surveyed dairy farms. This study concluded that large herd size with better dairy cow management facilities is crucial to produce quality milk with better dairy farm income.

Characteristics of Partial Oxidation Reforming with Various Sorts of Hydrocarbon Fuel (연료의 종류에 따른 부분산화 반응 특성에 관한 연구)

  • Park, Cheol-Woong;Choi, Young;Oh, Seung-Mook
    • Journal of the Korean Institute of Gas
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    • v.13 no.4
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    • pp.46-52
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    • 2009
  • Hydrogen can extend the lean misfire limit to a large extent when it is mixed with conventional fuels for an internal combustion engine. This study is about fuel reforming to produce hydrogen enriched gas as a fuel for engine. Especially gasoline, which consists of numerous hydrocarbon fuels, considered as source of reformed gas. Various hydrocarbons, including commercial fuel were reformed and potentialities of reformed gas on vehicles were accessed. The reforming efficiency and hydrogen yield were observed. Maximum hydrogen yield were found with different gas hourly space velocity(GHSV) and O2/C ratio of reforming conditions.

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Analysis of Waiting Time and its Associated Factors at School Lunch Room Using Ultrasonic and Noise Sensors (초음파와 소음 감지 센서를 이용한 학교 급식실 대기 시간과 연관 요소 분석)

  • Jung, Jimin;Shin, Yebin;Lee, Eunji;Kim, Jieun
    • Proceedings of the Korea Information Processing Society Conference
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    • 2019.10a
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    • pp.312-315
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    • 2019
  • 본 연구는 아두이노 보드와 다중 센서들을 사용하여 학교 급식실 대기 공간에서의 대기 상황을 분석한다. 실험에 사용한 초음파 및 소음 감지 센서들로부터 초음파 및 소음 데이터를 입력 받아 송신하는 아두이노 보드 기반 프로그램을 작성하고, 데이터를 수집, 저장, 관리하기 위하여 CoolTerm 프로그램을 사용한다. 또한, C 언어를 기반으로 정규화 프로그램과 필터링 프로그램을 구현하여 대기 인원 감지라고 인정할 수 있는 조건(일정 소음 이상 발생, 초당 5회 이상 감지 및 3미터 미만 거리에서 감지)에 맞지 않는 데이터를 걸러낸다. 예비 실험 이후 실시한 본 실험 범위는 8월 27일(화)부터 30일(금)까지 4일간, 점심 식사 시간 중 중간 시간대인 12시 20분부터 12시 39분까지이다. 분석 결과 식단 선호도에 따라 대기 시간에 확연한 차이가 발생하는 것을 확인하였으며, 배식 시간 역시 대기 시간에 미치는 영향이 있는 것을 알 수 있었다. 또한 초음파 센서로부터 분석한 결과와 소음 감지 센서로부터 분석한 결과, 상당한 유사성이 관찰되었다. 본 연구는 대기 시간만의 측정에 그치는 것이 아니라, 식단과 대기 시간과의 관계 분석을 통해 학생 식사 행태가 대기 시간에도 영향을 미친다는 추가적인 사실을 증명하였는데, 이는 대기 시간 문제 해결이 단순히 급식 대기 상황 개선에만 있는 것이 아니라 식단 및 배식 방식 등의 개선과 같이 이루어져야 함을 보여준다. 이는 기존 연구들이 확인하지 못했던 사실로, 본 연구의 주요한 기여로 볼 수 있다. 향후 본 연구를 확대하여 무선 인터넷 및 알림 시설을 갖춘다면, 현재의 학교 급식 환경을 획기적으로 개선할 수 있을 것으로 기대한다.

Influence of Temperature on Chloride Ion Diffusion of Concrete (콘크리트의 염화물이온 확산성상에 미치는 온도의 영향)

  • So, Hyoung-Seok;Choi, Seung-Hoon;Seo, Chung-Seok;Seo, Ki-Seog;So, Seung-Young
    • Journal of the Korea Concrete Institute
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    • v.26 no.1
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    • pp.71-78
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    • 2014
  • The long term integrity of concrete cask is very important for spent nuclear fuel dry storage system. However, there are serious concerns about early deterioration of concrete cask from creaking and corrosion of reinforcing steel by chloride ion because the cask is usually located in seaside, expecially by combined deterioration such as chloride ion and heat, carbonation. This study is to investigate the relation between temperature and chloride ion diffusion of concrete. Immersion tests using 3.5% NaCl solution that were controlled in four level of temperature, i.e. 20, 40, 65, and $90^{\circ}C$, were conducted for four months. The chloride ion diffusion coefficient of concrete was predicted based on the results of profiles of Cl- ion concentration with the depth direction of concrete specimens using the method of potentiometric titration by $AgNO_3$. Test results indicate that the diffusion coefficient of chloride ion increases remarkably with increasing temperature, and there was a linear relation between the natural logarithm values of the diffusion coefficients and the reciprocal of the temperature from the Arrhenius plots. Activation energy of concrete in this study was about 46.6 (W/C = 40%), 41.7 (W/C = 50%), 30.7 (W/C = 60%) kJ/mol under a temperature of up to $90^{\circ}C$, and concrete with lower water-cement ratio has a tendency towards having higher temperature dependency.

Development of a Core management Algorithm for Optimal Design of AMBIDEXTER Transient Cores (AMBIDEXTER 천이노심 설계최적화를 위한 노심관리 알고리즘 개발)

  • Yu, Geuk-Jong;Sin, Dong-Hun;So, Sun-Gyu;Lee, Yeong-Jun;Kim, Jin-Seong;O, Se-Gi
    • Proceedings of the Korean Nuclear Society Conference
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    • 2004.10a
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    • pp.99-100
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    • 2004
  • AMBIDEXTER-NEC의 천이노심은 $^{Nat}Th$$^{Nat}U$의 주입만으로 전 출력의 Break-even 노심에 도달하기위한 중간 단계이다. 선행연구에서 수행한 전 출력노심인 평형노심의 핵종수밀도에 도달하기 위해서 평형노심에서의 기저물질, 잠재핵분열성물질, 핵분열물질의 수밀도를 각 SEU-기반, Pu-기반, ADS-기반에서 그대로 유지하여 초기노심을 구성하였다. 또 각 시나리오에 대해 최대첨두출력과 원자로의 안전성을 고려해 Excess Reactivity를 5mk 내에서 초기노심을 결정하였다. 각 노심은 주 핵분열성물질 $^{235}U$, $^{239}Pu$$^{233}U$의 핵반응단면적 특성에 따라 평균 전환율이 각각 0.95, 0.83 및 1 .21 로서 핵연료물질의 적절한 선택만으로도 전환로, 연소로 및 증식로로 설계할 수 있음을 보여준다. 이러한 $Th/^{233}U$, U/Pu 핵연료주기를 사용하는 AMBIDEXTER-NEC 용융염핵연료 원자로의 초기노심에서 시작한 천이노심은 평형노심에장전할 충분한 $^{233}U$ 양을 확보해야 하므로 천이노심의 목표는 평형노심 $^{233}U$의 요구량에 최소한의 기간에 가장 적은 외부주입을 통해 도달하는 것이다. 천이노심에서 임계가 유지되는 AMBIDEXTER-NEC 원자로시스템의 3군 핵종변환 코드인 HELIOS-SQUID-AMBIBURN 체제를 개발하였고 그림 1.에 나타내었다. 이 알고리즘은 각 초기노심 중원소의 미시단면적, 중원소를 제외한 원소들의 거시단면적, 임계도를 만족하는 중성자속 및 외부주입율을 계산하여 SQUID 및 AMBIBURN 입력자료를 제공한다. 또한 일정시간 중원소의 핵종농도, 외부주입율과 중성자속이 일정하다는 가정 하 에 반복수행 하고 SEU-기반과 Pu-기반의 경우에는 각각 핵변환을 거쳐 재순환되는 $^{233}U$$^{239}Pu$의 양을 바로 주입하는 최대재순환 경우와 평형노심 요구 장전량에 이를 때까지 시설 내 저장하는 최소재순환 경우로 상황을 모사하였다. 그림 2 는 각 시나리오별 초기노심에서부터 200FPD까지 단위 용융염 체적당 $^{233}U$의 수밀도 시간변화를 나타낸 것이다. 그림을 보면 50일 이후부터는 수밀도의 변화가 일정한 기울기를 보이고 있고 재처리공정에서 $^{233}Pa$를 분리하는 최소재순환의 경우에는 최대재순환보다 2-3%정도에 지나지않아 그림에서 나타내지않았다. SEU-기반 및 Pu-기반에서 $^{233}U$의 증가율이 각각 2.54E+13, 2.81E+13 #/cc/d 로 Pu 기반이 조금 더 큰 증가율을 나타내고 있지만 평형노심 농도 1.04E+20 #/cc/d 에 도달하기 위해서는 두 경우 모두 매우 긴 시간이 걸릴 것을 예상할 수 있다. 요컨대 250MWth AMBIDEXTER-NEC가 평형노심을 이루기 위해 필요로 하는 $^{233}U$을 생산하는데 제안한 SEU-기반, Pu-기반 시나리오는 천이노심주기기간이 전형적인 원자로 수명 3-40년 보다 매우 큰 것으로 나타났다. 따라서 장전될 $^{233}U$의 확보를 위한 최적옵션은 초기노심부터 ADS와 같은 외부생산시설로부터 전량을 공급 받아 운전하는 것이라 판단된다.

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