• 제목/요약/키워드: overpressure

검색결과 164건 처리시간 0.023초

수소 취급시설 피해 저감을 위한 방호벽 설치 다목적 최적화 연구 (Multi-Objective Optimization Study of Blast Wall Installation for Mitigation of Damage to Hydrogen Handling Facility)

  • 오세현;안승효;김은희;마병철
    • 한국안전학회지
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    • 제38권6호
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    • pp.9-15
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    • 2023
  • Hydrogen is gaining attention as a sustainable and renewable energy source, potentially replacing fossil fuels. Its high diffusivity, wide flammable range, and low ignition energy make it prone to ignition even with minimal friction, potentially leading to fire and explosion risks. Workplaces manage ignition risks by classifying areas with explosive atmospheres. However, the effective installation of a blast wall can significantly limit the spread of hydrogen, thereby enhancing workplace safety. To optimize the wall installation of this barrier, we employed the response surface methodology (RSM), considering variables such as wall distance, height, and width. We performed 17 simulations using the Box-Behnken design, conducted using FLACS software. This process yielded two objective functions: explosion likelihood near the barrier and explosion overpressure affecting the blast wall. We successfully achieved the optimal solution using multi-objective optimization for these two functions. We validated the optimal solution through verification simulations to ensure reliability, maintaining a margin of error of 5%. We anticipated that this method would efficiently determine the most effective installation of a blast wall while enhancing workplace safety.

Development of scaling approach based on experimental and CFD data for thermal stratification and mixing induced by steam injection through spargers

  • Xicheng Wang;Dmitry Grishchenko;Pavel Kudinov
    • Nuclear Engineering and Technology
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    • 제56권3호
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    • pp.1052-1065
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    • 2024
  • Advanced Pressurized Water Reactors (APWRs) and Boiling Water Reactors (BWRs) employ a suppression pool as a heat sink to prevent containment overpressure. Steam can be discharged into the pool through multi-hole spargers or blowdown pipes in both normal and accident conditions. Direct Contact Condensation (DCC) creates sources of momentum and heat. The competition between these two sources determines the development of thermal stratification or mixing of the pool. Thermal stratification is of safety concern as it reduces the cooling capability compared to a completely mixed pool condition. In this work we develop a scaling approach to prediction of the thermal stratification in a water pool induced by steam injection through spargers. Experimental data obtained from large-scale pool tests conducted in the PPOOLEX and PANDA facilities, as well as simulation results obtained using validated codes are used to develop the scaling. Two injection orientations, namely radial injection through multi-hole Sparger Head (SH) and vertical injection through Load Reduction Ring (LRR), are considered. We show that the erosion rate of the cold layer can be estimated using the Richardson number. In this work, scaling laws are proposed to estimate both the (i) transient erosion velocity and (ii) the stable position of the thermocline. These scaling laws are then implemented into a 1D model to simulate the thermal behavior of the pool during steam injection through the sparger.

Strategic analysis on sizing of flooding valve for successful accident management of small modular reactor

  • Hyo Jun An;Jae Hyung Park;Chang Hyun Song;Jeong Ik Lee;Yonghee Kim;Sung Joong Kim
    • Nuclear Engineering and Technology
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    • 제56권3호
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    • pp.949-958
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    • 2024
  • In contrast to all-time flooded small modular reactor (SMR) systems, an in-kind flooding safety system (FSS) has been proposed as a passive safety system applicable to small modular reactors (SMRs) that adopt a metal containment vessel (MCV). Under transient conditions, the FSS can provide emergency cooling to dry reactor cavities and sustain long-term coolability using re-acquired evaporated steam in the reactor building on demand. When designing an FSS, the effect of the flooding flow area is vital as it affects the overall accident sequence and safety. Therefore, in this study, a MELCOR model of a reference SMR is developed and numerical analysis is performed under postulated accident scenarios. Without flooding, the MCV pressure of the reactor module exceeds the design pressure before core damage. To prevent core damage, an emergency flooding strategy is devised using various flow path parameters and requirements to ensure an adequate emergency coolant supply before the core damage is investigated. The results indicate that a flow area exceeding 0.02 m2 is required in the FSS to prevent MCV overpressure and core damage. This study is the first to report a strategic analysis for appropriately sizing an FSS flooding valve applicable to innovative SMRs.

아크릴로니트릴 누출에 따른 독성, 복사열 및 외부영향에 의한 아파트의 성능위주설계 방안 (Performance Based Design Plan for Apartment that Reflects External Effects from Toxicity and Radiant Heat Due to Acrylonitrile Leakage)

  • 오승주;한상훈;공하성
    • 대한안전경영과학회지
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    • 제26권2호
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    • pp.65-77
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    • 2024
  • This study aims to present a performance based design for apartments through evacuation safety assessment and damage impact assessment due to acrylonitrile leakage. In the evacuation safety evaluation, ASET was analyzed as 25 min or more and 60 min or less when the ventilation rate was once per hour, and RSET was 22.6 min. Evacuation safety is satisfied when the number of ventilation per hour is less than 1, so it is necessary to design the number of ventilation to be 1 or less. In the damage impact assessment, the 0% structural collapse rate due to overpressure was measured to be between 71m and 90m, and the 0% fatality rate due to radiant heat was measured to be between 136m and 353m. Therefore, maintain a safe distance of 353m or more.

산화프로필렌의 누출영향평가에 따른 안전거리 산정 (The Selter Selection Plan due to Formaldehyde Leakage)

  • 오승주;한상훈;공하성
    • 대한안전경영과학회지
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    • 제26권2호
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    • pp.11-22
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    • 2024
  • This study aims to present safety distances by the damage impact assessment of the leakage of propylene oxide. As a result of the experiment, the pressure 1psi range was 52m to 169m, the radiant heat 18kW/m2 range was 63m to 163m, the AEGL-2 range was analyzed as 224m to 414m, and the fire ball diameter was analyzed to be 45m to 121m. Additionally, the extent of damages was proportional to the amount of propylene oxide stored or handled. The safe distance for a 10% lethality due to overpressure and radiant heat was calculated to be 134m, and the safe distance for a 0% lethality was 169m. Toxicity was measured at 134m with a lethality 0%. Therefore, the safety distance due to leakage of propylene oxide is calculated to be between 134m and 169m.

플렉시블 CIGS 태양전지 제조를 위한 저온 나노입자공정 (Low Temperature Nanopowder Processing for Flexible CIGS Solar Cells)

  • 박진호;;;박준영
    • 한국신재생에너지학회:학술대회논문집
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    • 한국신재생에너지학회 2010년도 춘계학술대회 초록집
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    • pp.61.1-61.1
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    • 2010
  • $CuIn_{1-x}-GaxSe_2$ based materials with direct bandgap and high absorption coefficient are promising materials for high efficiency hetero-junction solar cells. CIGS champion cell efficiency(19.9%, AM1.5G) is very close to polycrystalline silicon(20.3%, AM1.5G). A reduction in the price of CIGS module is required for competing with well matured silicon technology. Price reduction can be achieved by decreasing the manufacturing cost and by increasing module efficiency. Manufacturing cost is mostly dominated by capital cost. Device properties of CIGS are strongly dependent on doping, defect chemistry and structure which in turn are dependent on growth conditions. The complex chemistry of CIGS is not fully understood to optimize and scale processes. Control of the absorber grain size, structural quality, texture, composition profile in the growth direction is important to achieving reliable device performance. In the present work, CIS nanoparticles were prepared by a simple wet chemical synthesis method and their structural and optical properties were investigated. XRD patterns of as-grown nanopowders indicate CIS(Cubic), $CuSe_2$(orthorhombic) and excess selenium. Further, as-grown and annealed nanopowders were characterized by HRTEM and ICP-OES. Grain growth of the nanopowders was followed as a function of temperature using HT-XRD with overpressure of selenium. It was found that significant grain growth occurred between $300-400^{\circ}C$ accompanied by formation of ${\beta}-Cu_{2-x}Se$ at high temperature($500^{\circ}C$) consistent with Cu-Se phase diagram. The result suggests that grain growth follows VLS mechanism which would be very useful for low temperature, high quality and economic processing of CIGS based solar cells.

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지하 매설 공동구 내부 가스 폭발에 대한 위험성 평가 (Quantitative Risk Assessment for Gas-explosion at Buried Common Utility Tunnel)

  • 장유리;정승호
    • 한국가스학회지
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    • 제20권5호
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    • pp.89-95
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    • 2016
  • 가스 배관을 공동구 내에 수용하는 것은 단순 매설하는 것보다 부식의 위험이 적고, 외부인의 출입이나 굴착공사 등으로부터 오는 물리적 손상을 예방할 수 있다는 점에서 편의성이 크다. 그러나 밀폐된 공간이라는 특성상 개방된 공간에서의 폭발보다 폭발 과압에 의한 피해가 크다. 그럼에도 공동구에 대한 연구는 화재 사고에 국한되어 진행되었고, 폭발로 인한 위험성에 관한 연구가 부족한 실정이다. 본 연구는 지하 공동구 내부의 가스배관으로부터 누출된 메탄가스가 원인모를 점화원에 의해 폭발을 일으켰을 경우를 가정하여 피해결과 관점에서 공동구 내부의 폭발이 상부 시설물에 미치는 영향을 살펴보았다. 안전설비의 작동상태에 따른 2가지의 시나리오를 선정하여 CFD tool인 FLACS를 사용하여 영향성 평가를 진행한 결과 대부분의 건축물을 전파 시킬 수 있을 정도의 폭발 과압이 예측되었다. 이 결과를 활용하여서 사고 발생 빈도를 감소시켜 안전성을 확보할 수 있는 추가 대책을 제시하였다.

LPG 충전소 내 설치된 방호벽의 효용성 평가 (An Availability Assessment of Protection Wall Installed in LPG Filling Station)

  • 이진한;조영도;문종삼;김래현
    • 한국가스학회지
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    • 제22권5호
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    • pp.38-45
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    • 2018
  • LPG충전소 내에서 발생하는 주요 사고는 제트화재, 풀화재, 증기운 폭발로 구분된다. 방호벽을 충전소 내에 설치하면, 제트화재 시나리오에 대해서는 복사열로 인한 피해를 경감할 수 있고 풀화재 시나리오에 대해서는 풀의 확장을 제한하는 효과를 얻을 수 있다. 또한 증기운 폭발 시에는 증기운의 확산과 폭발과압으로 인한 인명피해를 경감하는 효과를 얻을 수 있다. 본 연구에서는 제트화재, 풀화재, 증기운 폭발 등 LPG충전소에서 발생 가능한 사고 시나리오별로 방호벽의 피해경감 정도를 평가할 수 있는 방법을 제안하였으며, LPG충전소 내 방호벽의 효과성에 대해 사례연구를 수행하였다. 이를 통해 제트화재와 증기운 폭발 발생 시 방호벽 뒤에 위치한 수용체의 사망확률을 효과적으로 줄일 수 있다는 것을 보여준다.

원자로 노심 용융물의 고압분출 및 비산 현상에 대한 수치해석적 연구 (MOLTEN CORIUM DISPERSION DURING HYPOTHETICAL HIGH-PRESSURE ACCIDENTS IN A NUCLEAR POWER PLANT)

  • 김종태;김상백;김희동;정재식
    • 한국전산유체공학회:학술대회논문집
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    • 한국전산유체공학회 2009년 추계학술대회논문집
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    • pp.121-128
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    • 2009
  • During a hypothetical high-pressure accident in a nuclear power plant (NPP), molten corium can be ejected through a breach of a reactor pressure vessel (RPV) and dispersed by a following jet of a high-pressure steam in the RPV. The dispersed corium is fragmented into smaller droplets in a reactor cavity of the NPP by the steam jet and released into other compartments of the NPP by a overpressure in the cavity. The fragments of the corium transfer thermal energy to the ambient air in the containment or interact chemically with steam and generate hydrogen which may be burnt in the containment. The thermal loads from the ejected molten corium on the containment which is called direct containment heating (DCH) can threaten the integrity of the containment. DCH in a NPP containment is related to many physical phenomena such as multi-phase hydrodynamics, thermodynamics and chemical process. In the evaluation of the DCH load, the melt dispersion rates depending on the RPV pressure are the most important parameter. Mostly, DCH was evaluated by using lumped-analysis codes with some correlations obtained from experiments for the dispersion rates. In this study, MC3D code was used to evaluate the dispersion rates in the APR1400 NPP during the high-pressure accidents. MC3D is a two-phase analysis code based on Eulerian four-fields for melt jet, melt droplets, gas and water. The dispersion rates of the corium melt depending on the RPV pressure were obtained from the MC3D analyses and the values specific to the APR1400 cavity geometry were compared to a currently available correlation.

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액화수소 충전스테이션에서 VCE로 인한 피해영향평가에 관한 연구 (A Study on the Evaluations of Damage Impact due to VCE in Liquid Hydrogen Charging Station)

  • 이수지;천영우;이익모;황용우
    • 한국가스학회지
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    • 제21권5호
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    • pp.56-63
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    • 2017
  • 전세계적으로 수소 충전 스테이션 구축에 많은 투자와 지원을 하고 있는 실정이다. 그러나 수소는 폭발범위가 넓고 확산이 빠른 기체이다. 본 연구에서는 액화수소를 취급하는 소규모~대규모 충전스테이션을 대상으로, 사고시 발생하는 VCE로 인한 피해영향범위를 산출하고, 프로빗 모델을 통해 주변의 인적, 물적 피해를 예측하였다. 더불어, 벤트스택 끝단에서 발생 가능한 Jet fire를 시나리오로 선정하여 최적 높이를 설정하였다. 피해영향범위는 관심과압 6.9kPa을 기준으로 하여, 소규모 저장시설의 경우 8.24m, 중규모 14.10m, 대규모 22.38m이다. 폐출혈로 인한 인체 피해는 소규모와 중규모가 각각 50m, 대규모 100m였으며, 구조물 손상에 따른 피해는 소규모 200m, 중규모 300m 및 대규모 500m이다. 벤트스택의 최적높이는 소규모 4.7m, 중규모 8.8m 및 대규모 16.9m이다.