• Nuclear Engineering and Technology
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• 제56권3호
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• pp.1066-1080
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• 2024

SMART100 has a containment pressure and radioactivity suppression system (CPRSS) for passive containment cooling system (PCCS). This prevents overheating and over-pressurization of a containment through direct contact condensation in an in-containment refueling water storage tank (IRWST) and wall condensation in a CPRSS heat exchanger (CHX) in an emergency cool-down tank (ECT). The Korea Atomic Energy Research Institute (KAERI) constructed scaled-down test facilities, SISTA1 and SISTA2, for the thermal-hydraulic validation of the SMART100 CPRSS. Three separate effect tests were performed using SISTA1 to confirm the heat removal characteristics of SMART100 CPRSS. When the low mass flux steam with or without non-condensable gas is released into an IRWST, the conditions for mitigation of the chugging phenomenon were identified, and the physical variables were quantified by the 3D reconstruction method. The local behavior of the non-condensable gas was measured after condensation inside heat exchanger using a traverse system. Stratification of non-condensable gas occurred in large tank of the natural circulation loop. SISTA2 was used to simulate a small break loss-of-coolant accident (SBLCOA) transient. Since the test apparatus was a metal tank, compensations of initial heat transfer to the material and effect of heat loss during long-term operation were important for simulating cooling performance of SMART100 CPRSS. The pressure of SMART100 CPRSS was maintained below the design limit for 3 days even under sufficiently conservative conditions of an SBLOCA transient.

• 한국농공학회지
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• 제38권3호
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• pp.82-91
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• 1996

This is a basic study for the static and dynamic analysis on the elasto-plastic and elasto-viscoplastic of an axi-symmetric shell. The objective of this study was to investigate the mechanical characteristics of a nuclear reinforced concrete containment structure, which was selected as a model, by a numerical analysis using a finite element method. The structure was modeled with discrete ring elements of 8-noded isoparametric element rotating against the symmetrical axis, and the interaction between the foundation and the structure was modeled by Winkler's model. Also, the meridional tendon was modeled with 2-node truss elements, and the hoop tendon was done with point elements in two degrees of freedom. The effect of the tendon was considered without the increasement in total degree of freedom as the stiffness matrix of modeled tendon elements was assembled on the stiffness matrix of ring elements linked with the tendon. The results obtained from the analysis of an example were summarized as follows : 1. The stresses in the hoop direction on the interior and exterior surfaces of the structure were shown in changes of similar trend, and high stresses appeared on the structure wall 2. The stresses in the meridional direction on the interior and exterior surfaces were shown in change of different trend. Especially, the stresses at the junctions between the dome and the wall and between the wall and the bottom plate of the structure were very high, compared with those at other parts of the structure. 3. The stress changes in the direction of thickness on the crown of the dome were much linearly distributed. However, as the amount of tendon increased, the stresses in the upper and lower parts of the wall established with the tendon were shown stress concentration. 4. The stress changes in the direction of thickness on the center of the structure wall was linearly distributed in the all cases, and special stress due to the use of the tendon was not shown.

• 한국지반공학회:학술대회논문집
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• 한국지반공학회 1994년도 가을 학술발표회 논문집
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• pp.111-118
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• 1994

The use of steel sheet pile walls as barrier walls have the temporary for coffer dam, retaining wall in excavation, etc., but also permanent of semi-permanent for harbor construction, containment systems, vertical barrier systems for waste disposal (landfill) or subway in excavarion. In all these applicaions the resistance of the structure to seepage plays an important role. Also the stability and longevity of the construction, the possibility of permanent control and survey make the steel sheet pile wall a nearly perfect vertical barrier from a technical and economical point of view.

• Nuclear Engineering and Technology
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• 제27권3호
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• pp.281-291
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• 1995

이 연구의 목적은 수동형 격납용기 냉각계통의 용기 바깥표면이 건조 및 습한 조건일때 격납용기 내, 외벽에서 일어나는 열전달과정에 대한 실험적 자료를 얻는데 있다. 시험모델은 AP 600구조에 근거하여 격납용기의 둘레중 60$^{\circ}$부분만을 취하였다. 시험모델의 주요치수는 원형의 값을 대략 10분의 1로 축소한 것이다. 붕괴열을 모의하기 위하여 전기적으로 가열되는 증기발생기를 시험모델내에 설치하였다. 최대열유속은 8.91 kW/$m^2$ 이었다. 두 가지 형식의 시험이 수행되었다. 하나는 수막유동없이 공기만의 자연대류에 관한 시험이고 다른 하나는 수막유동과 공기의 자연대류가 동반된 증발열전달 시험이다. 시험결과 수막유동이 없는 경우 공기만의 자연대류 열전달 능력은 약 1.48 kW/$m^2$ 열유속에서 제한되고 있음을 알게 되었다 또한 수막유동과 공기의 자연대류가 동시에 일어나는 시험에서 열제거 능력은 현저히 향상됨을 알게 되었다 이들 열전달 측정치들을 기존 관계식들과 비교하였다.

• 한국전산구조공학회논문집
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• 제24권4호
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• pp.449-455
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• 2011

최근 가압중수형 원전 격납건물의 내압능력 및 비선형 거동에 관한 실증실험과 해석코드에 대한 검증을 위하여 인도의 BARC 주관으로 가압중수형 격납건물 1/4 축소모델을 건설하였고, 내압성능평가를 위한 국제공동연구가 수행되었다. 이 논문은 가압중수형 1/4 축소모델 격납건물에 대한 내압성능과 비선형 거동을 예측하기 위하여 유한요소해석을 수행하였고 그 결과를 도출하였다. 대상 격납건물은 기초매트와 원통형 벽체 및 돔으로 구성되어 있고, 수평 텐던의 정착을 위하여 4개의 부벽(buttress)을 가지고 있다. 유한요소해석을 위하여 ABAQUS를 이용하였고 콘크리트, 철근 및 텐던에 대한 유한요소 모델을 작성하여 극한내압해석을 수행하였다. 유한요소해석결과 콘크리트의 초기 균열은 $1.6P_d$(design pressure)에서 발생하였고, 철근의 항복은 $3.36P_d$ 그리고 극한내압능력은 $4.0P_d$ 수준으로 나타났다.

• 한국지반공학회:학술대회논문집
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• 한국지반공학회 2010년도 추계 학술발표회
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• pp.1264-1273
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• 2010

Soil-bentonite cutoff walls are widely recognized to be the effective barrier for containment of wastes and groundwater. Bentonite cake is usually found remaining on the trench surface due to the use of bentonite slurry during the excavation for the cutoff wall construction. Defects also inevitably take place due to the inappropriate construction procedures or improperly mixed soil-bentonite backfill. The defects include insufficient keys and windows in the soilbentonite cutoff wall. In this study, the performance of the soil-bentonite cutoff wall is evaluated based on the flow rates through the wall. Three-dimensional numerical models were applied to simulate the groundwater flow through the soil-bentonite cutoff walls of typical geometries with consideration of the defects and bentonite cake. Results of the simulations showed that the bentonite cake has no effect in the insufficient key cases. In the keyed wall cases, the bentonite cake with very low hydraulic conductivity significantly impedes the flow of groundwater through the wall. The presence of the bentonite cake not only compromises the window defect but also renders the wall construction more effective in blocking the groundwater flow. These findings show the significance of the bentonite cake in a soil-bentonite cutoff wall construction.

• 한국해양공학회지
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• 제26권2호
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• pp.1-7
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• 2012

DNV-OS-F101 includes the concept development, design, construction, operation,and abandonment of offshore pipeline systems. The main objective of this offshore standard (OS) is to ensure that pipeline systems are safe during the installation and operational period. The pipeline design philosophy also includes public safety and environmental protection. The mechanical wall thickness design of a pipeline shall follow the design objectives and safety philosophy. This new design code includes a very sophisticated design procedure to ensure a safe pipeline, public safety, and environmental protection. This paper presents the results of a parametric study for the wall thickness design of offshore pipelines. A design matrix was developed to cover the many design factors of pipeline integrity, public safety, and environmental protection. Sensitivity analyses of the various parameters were carried out to identify the impacts on offshore pipeline design.

• 한국콘크리트학회:학술대회논문집
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• 한국콘크리트학회 2002년도 봄 학술발표회 논문집
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• pp.475-480
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• 2002

Tension tests of six half-thickness concrete containment wall elements were conducted as part of a Korea Atomic Energy Research Institute (KARRI) program. The aim of the KAERI test program is providing a test-verified analytical method for estimating capacities of concrete reactor containment buildings under internal overpressurization from postulated degraded core accidents. The data from the tests reported herein should be useful for benchmarking method that requires modeling of material behavior including concrete cracking and reinforcement/concrete interaction exhibited by the test. Major test variable is the compressive strength of concrete and its effect on the behavior of prestressed concrete panel subjected to biaxial tension.

• Journal of Advanced Marine Engineering and Technology
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• 제40권2호
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• pp.112-119
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• 2016

Many studies have been conducted on the performance of a passive autocatalytic recombiner (PAR), but not many have focused on the locations where the PAR is installed. During a severe accident in a nuclear reactor containment, a large amount of hydrogen gas can be produced and released into the containment, leading to hydrogen deflagration or a detonation. A PAR is a hydrogen mitigation method that is widely implemented in current and advanced light water reactors. Therefore, for this study, a PAR was installed at different locations in order to investigate the difference in hydrogen reduction rate. The results indicate that the hydrogen reduction rate of a PAR is proportional to the distance between the hydrogen induction location and the bottom wall.

• 한국지진공학회:학술대회논문집
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• 한국지진공학회 1997년도 추계 학술발표회 논문집 Proceedings of EESK Conference-Fall 1997
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• pp.90-97
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• 1997

The purpose of this study is to evaluate the seismic response characteristics of Wolsong nuclear power plant (NPP) structures for the Kyeongju earthquake(ML=4.3) occurred on June 26, 1997. The seismograms are obtained from five accelerographs of nuclear power plant at Wolsong, Kyeongbuk. The distance from the epicenter is about 25km. The peak acceleration (PA) due to the earthquake is 0.0235g, which is far lower value than that of design basis earthquake(DBE). The PA at the containment wall is about twice as large as that at free field. Also, the higher the accelerograph is located in, the larger the PA is measured to be From the response spectrum analysis, the dominant frequency of the response is close to 4 Hz, which is similar to the free field is poor because of contamination by high frequency waves as a result of reflection and diffraction between ground and NPP structure. We are of opinion that the accelerograph at the free field should be moved approximately twice the building dimension away from the containment structure.