• 한국지반환경공학회 논문집
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• 제11권8호
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• pp.57-63
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• 2010

본 연구에서는 준설투기장의 설계를 위하여 실내시험으로 컬럼을 이용한 준설토 침강 자중압밀시험 및 상등수에 대한 부유물 농도시험을 수행하였으며, 현장조건과 배출수의 부유물 농도를 고려한 준설투기장을 설계 검토하였다. 준설투기장 폭과 목표 부유물 농도와의 관계 검토결과, 소요면적에서는 투기장 폭이 좁고 길이가 길수록 부유물 농도가 감소함을 알 수 있었다. 또한 준설투기가 진행됨에 따라 배출되는 상등수의 부유물 농도의 변화를 예측하기 위하여 침강허용깊이의 변화에 대한 영향도 고려되어야 하며, 이는 배출수의 목표 부유물 농도가 낮을수록 더욱 중요하다.

• Journal of Advanced Marine Engineering and Technology
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• 제40권3호
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• pp.165-173
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• 2016

2011년 3월 11일 리히터 스케일 9.0의 강진과 10-14m파도로 인해 Fukushima Daiichi(FD) 원자력 단지의 주전력과 보조전력이 끊어져 냉각장치가 작동하지 않았고 노심의 열이 제거되지 못해 폭발이 일어나는 사고가 발생했다. 노심의 열이 제거되지 못하면 핵연료 피복재인 지르칼로이(zircaloy)와 같은 금속이 고온 상태에서 수증기와 산화 반응하여 수소를 발생시킨다. 발생된 수소는 격납건물로 방출되는데 방출된 수소가 연소하는 경우 격납건물의 안정성에 영향을 줄 정도의 큰 충격을 유발할 수 있는 수소폭발로 이어질 수 있다. 본 연구에서는 격납건물 내부의 수소 분포를 분석한 연구 [1]에서 제시한 폭발의 위해도가 높은 영역에 대하여 폭발해석을 수행하였으며 수소 폭발이 격납건물의 건전성에 미치는 영향에 대하여 분석하였다. 격납건물 중앙부를 제외하고 수소폭발이 발생하였고 상부에 전체 수소의 40%이상이 모였을 때와 하부 좌측, 우측의 격벽사이에 수소가 모였을 때 큰 폭발이 발생했으며 격납건물 벽면에 큰 응력을 동반하였다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1995년도 추계학술발표회논문집(1)
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• pp.358-363
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• 1995

A study on passive cooling systems for concrete containment of advanced pressurized water reactors has been performed. The proposed passive containment cooling system (PCCS) consist of (1) condenser units located inside containment, (2) a steam condensing pool outside containment at higher elevation, and (3) downcommer/riser piping systems which provide coolant flow paths. During an accident causing high containment pressure and temperature, the steam/air mixture in containment is condensed on the outer surface of condenser tubes transferring the heat to coolant flowing inside tubes. The coolant transfers the heat to the steam condensing pool via natural circulation due to density difference. This PCCS has the following characteristic: (1) applicable to concrete containment system, (2) no limitation in plant capacity expansion, (3) efficient steam condensing mechanism (dropwise or film condensation at the surface of condenser tube), and (4) utilization of a fully passive mechanism. A preliminary conceptual design work has been done based on steady-state assumptions to determine important design parameter including the elevation of components and required heat transfer area of the condenser tube. Assuming a decay power level of 2%, the required heat transfer area for 1,000MWe plant is assessed to be about 2,000 ㎡ (equivalent to 1,600 of 10 m-long, 4-cm-OD tubes) with the relative elevation difference of 38 m between the condenser and steam condensing pool and the riser diameter of 0.62 m.

• 한국분무공학회지
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• 제4권3호
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• pp.42-52
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• 1999

An effectiveness of thermal utilization of a dousing system in the 600 MW PHWR Nuclear Power Plant has been evaluated. The behavior and conditions of water droplet sprayed in a postulated accident conditions in containment configuration has been calculated. In this calculation, two pressure conditions with the consideration of obstruction area and containment wall effect has been established : one being the minimum containment pressure of 7 kPa(g) encountered for dousing shut off and the other being the containment design pressure 124 kPa(g). The results revealed that the effectiveness of the thermal utilization ranges from 93% to 97%. In the analysis on two cases without/with side wall effect in the containment building, the thermal utilization decreases with obstruction area from 89% to 85%, which satisfies the design criteria set for the containment pressure against the accident condition.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2007년도 추계학술대회논문집
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• pp.1197-1202
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• 2007

The paper deals with the structural analysis and vibration test for the scaffolding system of LNG cargo containment. The eight-stories scaffolding system has telescopic area, working area, coner area and storage area in real system. In the structural analysis, the maximum displacement and stress of the each floor for the scaffolding system are investigated by finite element method. In the vibrational analysis, the natural frequencies and mode shapes for 8-stories scaffolding system of the LNG cargo containment are investigated. In order to compare theoretical natural frequencies with experimental ones, small size of 2-step scaffolding structure is used, and the theoretical results for natural frequency have a good agreement with experimental ones.

• 한국소음진동공학회논문집
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• 제20권6호
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• pp.546-554
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• 2010

The paper deals with the structural analysis and vibration test for the scaffolding system of LNG cargo containment. The eight-stories scaffolding system has telescopic area, working area, coner area and storage area in real system. In the structural analysis, the maximum displacement and stress of the each floor for the scaffolding system are investigated by finite element method. In the vibrational analysis, the natural frequencies and mode shapes for 8-stories scaffolding system of the LNG cargo containment are investigated. In order to compare theoretical natural frequencies with experimental ones, small size of 2-step scaffolding structure is used, and the theoretical results for natural frequency have a good agreement with experimental ones.

• 한국지하수토양환경학회:학술대회논문집
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• 한국지하수토양환경학회 1998년도 공동 심포지엄 및 추계학술발표회
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• pp.81-85
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• 1998

In the present study, the design method of containment walls is proposed by utilizing an existing site. The selected remedy for the Source Area of Operable Unit 2 at Hill Air Force Base stipulated containment of the pure-phase trichloroethylene contamination. The in-place-mixed wall construction was selected because of the irregular topography, small area of the site, and the requirement to reach depths of greater than 90 feet below ground surface. Bench-scale compatibility studies were performed for the containment wall mix design on three commercial bentonite clays. The samples were subject to screening tests and long-term tests for evaluation of changed soil properties when exposed to the contaminated groundwater.

• Nuclear Engineering and Technology
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• 제49권5호
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• pp.941-952
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• 2017

Using the Generation of Thermal-Hydraulic Information for Containments (GOTHIC) code, thermal-hydraulic phenomena that occur inside the containment have been investigated, along with the preliminary design of the passive containment cooling system (PCCS) of an innovative pressurized water reactor (PWR). A GOTHIC containment model was constructed with reference to the design data of the Advanced Power Reactor 1400, and report related PCCS. The effects of the design parameters were evaluated for passive containment cooling tank (PCCT) geometry, PCCS heat exchanger (PCCX) location, and surface area. The analyzed results, obtained using the single PCCT, showed that repressurization and reheating phenomena had occurred. To resolve these problems, a coupled PCCT concept was suggested and was found to continually decrease the containment pressure and temperature without repressurization and reheating. If the installation level of the PCCX is higher than that of the PCCT, it may affect the PCCS performance. Additionally, it was confirmed that various means of increasing the external surface area of the PCCX, such as fins, could help improve the energy removal performance of the PCCS. To improve the PCCS design and investigate its performance, further studies are needed.

• 한국지반환경공학회 논문집
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• 제11권10호
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• pp.41-48
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• 2010

본 연구에서는 기존에 적용된 준설투기장 설계에서 준설투기장에서 배출되는 상등수의 부유물 농도 예측에 대한 적합성 평가를 위하여 실제 현장 준설 시 준설투기장 내에서 준설토의 입도분포 및 상등수의 부유물 농도 분포를 측정하여 설계 예측 값과 비교하였으며, 상등수의 유속과 부유물 농도와의 관계를 분석하였다. 평가 결과, 현장 측정값과 설계 예측값이 비교적 유사한 경향을 보였으나, 준설 초기 및 상등수 유속이 증가한 시점에서는 설계 예측값과 상이한 측정값을 보였다. 이는 기존에 적용된 준설투기장 설계법이 준설 기간에 따라 민감하게 변화하는 준설토의 침강 깊이 및 상등수의 유속 등을 반영하지 못하기 때문으로 판단된다. 또한 준설투기장에서 동시에 측정된 유속과 부유물 농도의 분포가 유사한 경향을 보이므로 상등수의 유속과 부유물 침전이 상당히 밀접한 관계가 있는 것으로 관측되었다. 따라서, 현장 준설투기장 상황 변화를 보다 정확히 예측하기 위하여 준설토 계면고, 침강깊이, 상등수 유속에 따라 변화하는 부유물 침전을 고려한 준설투기장 설계법이 필요하다고 사료된다.

• Nuclear Engineering and Technology
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• 제54권8호
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• pp.2960-2973
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• 2022

Since Fukushima nuclear power plant (NPP) accident in 2011, the importance of research on various severe accident phenomena has been emphasized. Particularly, detailed analysis of combustion risk is necessary following the containment damage caused by combustion in the Fukushima accident. Many studies have been conducted to evaluate the risk of local hydrogen concentration increases and flame propagation using computational code. In particular, the potential for combustion by local hydrogen concentration in specific areas within the containment has been emphasized. In this study, the process of flame propagation generated inside a reactor core to containment during a loss of coolant accident (LOCA) was analyzed using MELCOR 2.1 code. Later in the LOCA scenario, it was expected that hydrogen combustion occurred inside the reactor core owing to oxygen inflow through the cold leg break area. The main driving force of the oxygen intrusion is the elevated containment pressure due to the molten corium-concrete interaction. The thermal and mechanical loads caused by the flame threaten the integrity of the containment. Additionally, the containment spray system effectiveness in this situation was evaluated because changes in pressure gradient and concentrations of flammable gases greatly affect the overall behavior of ignition and subsequent containment integrity.