• 제목/요약/키워드: Water Hydraulics

검색결과 232건 처리시간 0.027초

수질 및 수생태계 보전을 위한 세기 지속가능한 환경정책 방안 (The 21st Sustainable Environmental Policies for Protecting the Water Quality and Aquatic Ecosystems)

  • 김이형;이소영;민경석
    • 한국습지학회지
    • /
    • 제10권2호
    • /
    • pp.53-66
    • /
    • 2008
  • 환경부는 최근 30년 동안 가정하수, 축산폐수 및 산업폐수 등과 같은 점오염원에 대한 집중적인 기술개발, 시설설치 및 시설개선에 투자를 하여왔으며, 수질개선도 크게 이루어졌다. 그러나 지속적인 인간의 활동 및 토지이용의 고도화로 나타나는 도시화는 유역의 변화를 가져오고 수질 및 수생태계의 건전성을 약화시키는 새로운 오염물질을 유발하고 있다. 이러한 유역의 변화는 주로 인간의 활동공간을 창출하는 개발사업에 의하여 발생한다. 따라서 환경부는 시대적 필요에 의해 수질 및 수생태계 보전에 관한 법률 등의 개정을 통해 다양한 수질 및 유역관리제도(수질오염총량관리제, 비점오염원 관리지역 지정제도, 비점오염원설치신고제도, 고랭지 경작지 경작방법 권고 등)를 도입하여 수질개선을 꾀하고 있다. 그러나 이러한 각종 제도는 개발사업에 효율이 검증되지 않은 허울뿐인 비점저감시설의 난립을 가져올 소지가 매우 높다. 즉, 수질 및 수생태계의 보전은 환경에의 직접적 영향을 끼치는 개발사업의 건설기술 자체가 환경에 영향을 최소화시키는 건설환경기술로 변화될 때 가능하다. 따라서, 본 논문에서는 수질 및 수생태계 보전을 위한 유역관리기법, Low Impact Development(LID) 기술 및 비점오염원 관리 방향에 관한 21세기형 지속가능한 환경정책을 제안하고자 한다.

  • PDF

ROLE OF PASSIVE SAFETY FEATURES IN PREVENTION AND MITIGATION OF SEVERE PLANT CONDITIONS IN INDIAN ADVANCED HEAVY WATER REACTOR

  • Jain, Vikas;Nayak, A.K.;Dhiman, M.;Kulkarni, P.P.;Vijayan, P.K.;Vaze, K.K.
    • Nuclear Engineering and Technology
    • /
    • 제45권5호
    • /
    • pp.625-636
    • /
    • 2013
  • Pressing demands of economic competitiveness, the need for large-scale deployment, minimizing the need of human intervention, and experience from the past events and incidents at operating reactors have guided the evolution and innovations in reactor technologies. Indian innovative reactor 'AHWR' is a pressure-tube type natural circulation based boiling water reactor that is designed to meet such requirements, which essentially reflect the needs of next generation reactors. The reactor employs various passive features to prevent and mitigate accidental conditions, like a slightly negative void reactivity coefficient, passive poison injection to scram the reactor in event of failure of the wired shutdown systems, a large elevated pool of water as a heat sink inside the containment, passive decay heat removal based on natural circulation and passive valves, passive ECC injection, etc. It is designed to meet the fundamental safety requirements of safe shutdown, safe decay heat removal and confinement of activity with no impact in public domain, and hence, no need for emergency planning under all conceivable scenarios. This paper examines the role of the various passive safety systems in prevention and mitigation of severe plant conditions that may arise in event of multiple failures. For the purpose of demonstration of the effectiveness of its passive features, postulated scenarios on the lines of three major severe accidents in the history of nuclear power reactors are considered, namely; the Three Mile Island (TMI), Chernobyl and Fukushima accidents. Severe plant conditions along the lines of these scenarios are postulated to the extent conceivable in the reactor under consideration and analyzed using best estimate system thermal-hydraulics code RELAP5/Mod3.2. It is found that the various passive systems incorporated enable the reactor to tolerate the postulated accident conditions without causing severe plant conditions and core degradation.

PHABSIM을 이용한 복하천 하류 구간의 피라미 생애주기별 물리적 서식처 평가 (Physical Habitat Assessment of Bokha Downstream Reach Considering Life Cycle Stages of Zacco platypus Using PHABSIM)

  • 이혁진;박진석;장성주;홍록기;송인홍
    • 한국농공학회논문집
    • /
    • 제64권4호
    • /
    • pp.55-64
    • /
    • 2022
  • The objectives of this study were to assess physical habitat suitability of fish species for different life cycle stages and to suggest appropriate ecological stream flows in a Bokha downstream reach. A dominant species of Zacco platypus was selected as the study fish of which three stages of spawning, juvenile and adult in life cycle were considered into assessment. The stream hydraulic environment was calibrated with HEC-RAS before the PHABSIM simulation. The hydraulics of flow velocity and depth were used to estimate Weighted Usable Area (WUA) by multiplying respective habitat suitability indices with stream area. Overall the WUAs tend to be great in gentle slopes with relatively shallow water depth regions. Maximum WUAs, ie, candidate for ecological flow rates were 1 m3/s, 7 m3/s and 8 m3/s for the respective spawning, juvenile and adult stages of Zacco platypus. Since the ecological flow rates for juvenile and adult stages appeared to be is greater than the abundant flow rate (3.67 m3/s) for the study reach, additional water supply may be needed but should be cautious to avoid the spawning period of Apr through May from the stream water management perspective.

농업용 저수지 이수안전도 기준의 적정성 평가 (Evaluation of Water Supply Reliability Method for Agricultural Reservoirs)

  • 양미혜;남원호;문영식;신지현;양희충
    • 한국수자원학회:학술대회논문집
    • /
    • 한국수자원학회 2022년도 학술발표회
    • /
    • pp.512-512
    • /
    • 2022
  • 국내 수자원 시스템은 이수 관련 기준과 이를 평가할 수 있는 지표 및 방법, 지침이 미흡한 실정으로 관련 시설물의 안정성과 형평성에 대한 문제가 제기되어 왔다. 농업용 저수지의 경우 한발 시 관개용수를 공급할 수 있는 내한능력, 기존 설계기준에 의한 물수지법에 따른 저수지의 설계한발빈도를 대체 사용하여 이수안전도를 산정하고 있으며, 설계한발빈도인 10년 한발빈도는 10년에 1회 정도의 갈수를 기준으로 한다. 농업용 저수지의 축조년도는 1940-1970년대로 약 86%가 축조된 지 50년 이상 경과하였고, 대부분 설계 한발빈도가 10년 이하로 축조되었으나 최근 발생하고 있는 기후변화, 용수관리 환경 변화, 수요량의 변화, 설계한발빈도 변화 등으로 현시점의 이수안전도 파악이 필요한 실정이다. 본 연구에서는 국가물관리기본계획에서 준용하고 있는 신뢰도 관련 이수안전도 기준인 이수안전율과 공급신뢰율을 활용하여 농업용 저수지의 이수안전도를 산정하고 기존 농업용 저수지의 이수안전도 기준인 10년 한발빈도와 비교함으로써, 농업용 저수지 이수안전도 산정기준의 적정성을 평가하고자 한다. 신뢰도 기준은 장기간 계획기간 동안 저수지의 용수부족이 얼마나 발생하는가에 대한 평가 방법으로 이수안전율은 최대 부족량과 수요량으로 산정가능한 양적기준 신뢰도이며, 공급신뢰율은 물공급부족기간으로 산정가능한 시간기준 신뢰도이다. 신뢰도 기준에 의한 방법은 저수지 모의 운영을 통한 물수지 분석을 실시하여 산정이 가능하며, 물수지 분석을 위해 한국농어촌공사에서 개발한 수리수문설계시스템 (K-HAS, Hydraulics & Hydrology Analysis System)을 사용하였다. 본 연구의 결과는 농업용 저수지의 이수관리 계획 수립 및 내한능력 평가 등 국가수자원정책의 지표로 활용할 수 있을 것으로 기대된다.

  • PDF

저수지 플러싱 방류 효과분석을 위한 비정상상태 하천수질모형의 적용 (Application of an Unsteady River Water Quality Model for the Analysis of Reservoir Flushing Effect on Downstream Water Quality)

  • 정세웅
    • 한국수자원학회논문집
    • /
    • 제37권10호
    • /
    • pp.857-868
    • /
    • 2004
  • 갈수기 동안 우리나라 하천의 자정능력은 상류 댐으로부터 공급되는 하천유지유량에 큰 영향을 받으므로, 하천과 저수지시스템의 운영은 수량공급측면뿐만 아니라 하천의 수질과 생태계를 동시에 고려해야 한다. 본 연구에서는 수질사고와 악화에 취약한 갈수기 동안 다양한 댐 방류 대안이 하류 수질에 미치는 영향을 평가하기 위한 비정상상태 하천수질모형인 KORIV1-WIN을 개발하고 금강수계에 위치한 대청댐 하류구간을 대상으로 2002년 9월과 10월에 실측한 유량과 수질자료를 이용하여 보정과 검증을 각각 수행하였다. 그리고 대청댐의 단기간 플러싱 방류가 하류하천의 수질변화에 미치는 영향을 조사하기 위해 2003년 11월22일에 댐 방류량을 30 $m^3$/s에서 200 $m^3$/s로 6시간동안 증가시켜 수리와 수질실험을 실시하였으며, 모형의 성능을 검증하기 위해 플러싱 방류 사상 동안 하천의 수리특성과 수질변화를 모의하고 실측자료와 비교하였다 모형은 댐 방류량의 주요지점 도달시간과 수위상승을 잘 모의하였으며, 암모니아성 질소와 용존 인 등 질소와 인계통의 수질변화도 비교적 잘 예측하였다. 그러나 탄소계 유기물질로 인해 발생하는 산소요구량의 모의에서 실측자료와 큰 편차를 보였으며 이것은 댐 방류량이 하천을 통과할 때 하천 저니층으로부터 재부상한 유기물질의 영향을 모형에서 적절히 반영하지 못한 때문으로 판단된다.

대형냉각재 상실사고 재관수 기간 동안, 차세대 원자로 강수부 내의 열수력 현상 모의를 위한 실험장치 척도해석 (Scaling Analysis of Thermal Hydraulics Phenomena in the Nuclear Reactor Vessel Downcomer during the Reflood Phase of LBLOCA)

  • 윤병조;송철화;권태순;어동진;주인철;윤영중
    • 대한기계학회:학술대회논문집
    • /
    • 대한기계학회 2001년도 춘계학술대회논문집D
    • /
    • pp.821-827
    • /
    • 2001
  • As one of the advanced design features of the Korea next generation reactor, direct vessel injection (DVI) system is being considered instead of conventional cold leg injection (CLl) system. It is known that the DVI system greatly enhances the reliability of the emergency core cooling (ECC) system. However, there is still a dispute on its performance in terms of water delivery to the reactor core during the reflood period of a large-break loss-of-coolant accident (LOCA). Thus, experimental validation is under progress. In this paper, a new scaling method, using time and velocity reduced linear scaling law, is suggested for the design of a scaled-down experimental facility to investigate the direct ECC bypass phenomena in PWR downcomer.

  • PDF

Thermal-Hydraulic Test Facilities and Some Test Results of Integrated Heating Reactors

  • Jia, Haijun;Wu, Shaorong;Jiang, Shengyao
    • 한국원자력학회:학술대회논문집
    • /
    • 한국원자력학회 1996년도 추계학술발표회논문집(1)
    • /
    • pp.211-216
    • /
    • 1996
  • Since the middle of the eighties of this century a research program both for heating reactor and investigation of heating reactor thermal-hydraulics has been carried out in Institute of Nuclear Energy Technology(INET) of Tsinghua university in China. This kind of heating reactor is a light water cooled and integrated natural circulation reactor with low system pressure and low quality at the exit of core. Because of relatively long riser and low system pressure. a little change of the quality at the exit of the core will result in a relatively large variation of void fraction in the riser. Two full scale test loops. HRTL-5 and HRTL-200 simulating the HR-5 and HR-200 heating reactors in geometry and operation parameters respectively, and some test results from the HRTL-200 test facility are shown in this paper. The range of studied system pressure is from 1.0MPa to 4.0MPa, the largest heat flux is about 50 W/cm2, and the quality at the exit of test section is less than 5%.

  • PDF

SPH Modeling of Hydraulics and Erosion of HPTRM Levee

  • Li, Lin;Rao, Xin;Amini, Farshad;Tang, Hongwu
    • Journal of Advanced Research in Ocean Engineering
    • /
    • 제1권1호
    • /
    • pp.1-13
    • /
    • 2015
  • Post-Katrina investigations revealed that most earthen levee damage occurred on the levee crest and landward-side slope as a result of either wave overtopping, storm surge overflow, or a combination of both. In this paper, combined wave overtopping and storm surge overflow of a levee embankment strengthened with high performance turf reinforcement mat (HPTRM) system was studied in a purely Lagrangian and meshless approach, two-dimensional smoothed particle hydrodynamics (SPH) model. After the SPH model is calibrated with full-scale overtopping test results, the overtopping discharge, flow thickness, flow velocity, average overtopping velocity, shear stress, and soil erosion rate are calculated. New equations are developed for average overtopping discharge. The shear stresses on landward-side slope are calculated and the characteristics of soil loss are given. Equations are also provided to estimate soil loss rate. The range of the application of these equations is discussed.

Theoretical formulation of double scalar damage variables

  • Xue, Xinhua;Zhang, Wohua
    • Computers and Concrete
    • /
    • 제19권5호
    • /
    • pp.501-507
    • /
    • 2017
  • The predictive utility of a damage model depends heavily on its particular choice of a damage variable, which serves as a macroscopic approximation in describing the underlying micromechanical processes of microdefects. In the case of spatially perfectly randomly distributed microcracks or microvoids in all directions, isotropic damage model is an appropriate choice, and scalar damage variables were widely used for isotropic or one-dimensional phenomenological damage models. The simplicity of a scalar damage representation is indeed very attractive. However, a scalar damage model is of somewhat limited use in practice. In order to entirely characterize the isotropic damage behaviors of damaged materials in multidimensional space, a system theory of isotropic double scalar damage variables, including the expressions of specific damage energy release rate, the coupled constitutive equations corresponding to damage, the conditions of admissibility for two scalar damage effective tensors within the framework of the thermodynamics of irreversible processes, was provided and analyzed in this study. Compared with the former studies, the theoretical formulations of double scalar damage variables in this study are given in the form of matrix, which has many features such as simpleness, directness, convenience and programmable characteristics. It is worth mentioning that the above-mentioned theoretical formulations are only logically reasonable. Owing to the limitations of time, conditions, funds, etc. they should be subject to multifaceted experiments before their innovative significance can be fully verified. The current level of research can be regarded as an exploratory attempt in this field.

임계열유속 향상을 위한 나노물질의 산화처리에 대한 연구 (Study on the Oxidation Treatment of Nanoparticles for the Critical Heat Flux)

  • 김우중;전용한;김남진
    • 한국태양에너지학회 논문집
    • /
    • 제37권6호
    • /
    • pp.39-49
    • /
    • 2017
  • Pool boiling, one of the key thermal-hydraulics phenomena, has been widely studied for improving heat transfer efficiencies and safety of nuclear power plants, refrigerating systems, solar-collector heat pipes, and other facilities and equipments. In the present study, the critical heat flux (CHF) and heat-transfer coefficients were tested under the pool-boiling state using graphene M-5 and M-15 nanofluids as well as oxidized graphene M-5 nanofluid. The results showed that the highest CHF increase for both graphene M-5 and M-15 was at the 0.01% volume fraction and, moreover, that the CHF-increase ratio for small-diameter graphene M-5 was higher than that for large-diameter graphene M-15. Also at the 0.01% volume fraction, the oxidized graphene M-5 nanofluid showed a 41.82%-higher CHF-increase ratio and a 26.7%-higher heat-transfer coefficient relative to the same nanofluid without oxidation treatment at the excess temperature where the CHF of distilled water occurs.