• Computers and Concrete
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• 제19권2호
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• pp.211-216
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• 2017

Crack on concrete surface allows more rapid penetration of chlorides. Crack width and depth are dominant parameters for chloride behavior, however their effects on chloride penetration are difficult to quantify. In the present work, the previous anisotropic (1-D) model on chloride diffusion in concrete with single crack is improved considering crack shape and roughness. In the previous model, parallel-piped shape was adopted for crack shape in steady-state condition. The previous model with single crack is improved considering wedge shape of crack profile and roughness. For verifying the proposed model, concrete samples for nuclear power plant are prepared and various crack widths are induced 0.0 to 1.2 mm. The chloride diffusion coefficients in steady-state condition are evaluated and compared with simulation results. The proposed model which can handle crack shape and roughness factor is evaluated to decrease chloride diffusion and can provide more reasonable results due to reduced area of crack profile. The roughness effect on diffusion is evaluated to be 10-20% of reduction in chloride diffusion.

• Nuclear Engineering and Technology
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• 제29권6호
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• pp.444-450
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• 1997

The current ASME code for reinforced concrete containment structures are not based on probability concepts. The stochastic nature of natural hazard or accidental loads and the variations of material properties require a probabilistic approach for a rational assessment of structural safety and performance. The paper develops design load factors for the serviceability limit state of reinforced concrete containment structures. The target limit state probability is determined and the load factors are calculated by the numerical analysis. Design load factors are proposed and carried out the reliability assessments.

• 대한토목학회논문집
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• 제32권5A호
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• pp.277-287
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• 2012

지금까지 수행된 개구부가 존재하는 벽체에 대한 연구는 대부분 RC 벽체에 대해서 수행되었으며, SC(Steel plate Concrete) 벽체에 설치되는 개구부에 대한 연구는 수행된 예가 적다. 최근에 국내에서 개발된 SC 벽체는 원전구조물에 일부 적용되고 있지만, 관련 설계기준인 KEPIC-SNG에서도 개구부를 갖는 SC 벽체에 대한 설계법은 명확하게 정의되지 않았다. 본 연구에서는 원전구조물내 벽체에 설치되는 SC 벽체를 대상으로 개구부가 구조내력에 미치는 영향을 해석적 방법에 의해서 평가하였다. 비선형 해석 결과, 개구부가 설치되는 SC 벽체는 개구부 주변의 보강 여부가 내력에 미치는 영향이 크기 때문에 개구부 주변에 일정범위 이상의 보강이 이루어져야 하며, 개구부 주변이 보강된 경우는 개구부의 형상, 크기, 위치 및 설치개수에 관계없이 충분한 내력 및 연성을 확보할 수 있는 것으로 나타났다.

• Nuclear Engineering and Technology
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• 제47권5호
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• pp.633-645
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• 2015

In order to analyze the mechanical properties of two-way different configurations of prestressed concrete members subjected to axial loading, a finite element model based on the nuclear power plant containments is demonstrated. This model takes into account the influences of different principal stress directions, the uniaxial or biaxial loading, and biaxial loading ratio. The displacement-controlled load is applied to obtain the stress estrain response. The simulated results indicate that the differences of principal stress axes have great effects on the stress-strain response under uniaxial loading. When the specimens are subjected to biaxial loading, the change trend of stress with the increase of loading ratio is obviously different along different layout directions. In addition, correlation experiments and finite element analyses were conducted to verify the validity and reliability of the analysis in this study.

• 콘크리트학회지
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• 제28권5호
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• pp.8-14
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• 2016

• 한국건축시공학회지
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• 제15권6호
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• pp.653-660
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• 2015

Technologies for reducing construction duration are key factors in nuclear power plant construction projects, as a reduction in construction duration at the construction phase leads to a reduction in construction cost and an increase in profits through the early operation of the nuclear power plant. To analyze the constructability of the height of single-layer placement of formwork for the Reactor Containment Building (RCB) exterior wall through lateral pressure according to the height of concrete placement, the deformation criteria for formwork, and a new form design, 'MIDAS GEN (hereinafter referred to as MIDAS)' is used in this study. The cost and workload of formwork are derived according to the unit of height of the RCB exterior wall. Based on the result, it was found that the higher the RCB exterior wall, the higher the material cost, and the less the construction duration and the less the total number of formwork layers. Based on this result, it is believed that the material cost and the construction duration can be appropriately determined according to the formwork height.

• 한국전산구조공학회논문집
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• 제24권3호
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• pp.343-351
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• 2011

원자로 격납건물은 원자력발전소에서 발생가능한 모든 비상사태에 대한 최후의 방벽 역할을 하고 있다. 따라서 사고발생시 원자로 격납건물의 극한능력을 판단하는 것은 매우 중요하다. 대표적인 고려사항 가운데 하나인 LOCA사고 발생시 CANDU형 원자로 격납건물의 극한능력을 파악하기 위해서는 구조적 안전성 평가를 위한 구조해석이 필요하다. CANDU형 원자로 격납건물은 돔과 원통형벽체로 구성된 프리스트레스 콘크리트 쉘 구조물로서 부착식 텐돈을 사용하고 있다. 본 논문에서는 극한내압능력의 평가를 위하여 3차원 구조해석시스템을 사용한 프리스트레스 콘크리트 격납건물의 비선형해석을 수행하였다.

• 한국구조물진단유지관리공학회 논문집
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• 제21권6호
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• pp.83-90
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• 2017

원전콘크리트는 두꺼운 벽체를 가진 매스콘크리트 구조이며 시공초기에 건조수축 및 수화열에 따른 균열이 발생하기 쉽다. 또한 냉각수를 항상 필요로 하므로 해안가에 위치하는데, 균열이 발생한 콘크리트에서는 염화물 이온의 유입으로 인해 철근 부식이 빠르게 발생한다. 본 연구에서는 6000 psi 급 고강도 원전콘크리트 배합을 이용하여 재령 및 균열에 따른 확산계수의 변화를 분석하였다. 이를 위해 재령 56일, 180일, 365일 동안 양생된 콘크리트에 균열폭을 0.0~1.4 mm까지 유도하였으며 정상상태의 촉진 확산실험을 수행하였다. 균열폭의 증가에 따라 확산계수는 최대 2.7~3.1배로 증가하였으며, 재령의 증가에 따른 확산계수의 저감성이 크게 평가되었다. 또한 180일 동안 비말대에 노출된 균열부 콘크리트에 대하여 겉보기 확산계수 및 표면염화물량을 평가하였으며, 촉진 실험결과와 비교를 수행하였다.

• 방사성폐기물학회지
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• 제20권1호
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• pp.13-22
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• 2022

The decommissioning of a nuclear power plant generates large amounts of radioactive waste, which is of several types. Radioactive concrete powder is classified as low-level waste, which can be disposed of in a landfill. However, its safe disposal in a landfill requires that it be immobilized by solidification using cement. Herein, a safety assessment on the disposal of solidified radioactive concrete powder waste in a conceptual landfill site is performed using RESRAD. Furthermore, sensitivity analyses of certain selected input parameters are conducted to investigate their impact on exposure doses. The exposure doses are estimated, and the relative impact of each pathway on them during the disposal of this waste is assessed. The results of this study can be used to obtain information for designing a landfill site for the safe disposal of low-level radioactive waste generated from the decommissioning of a nuclear power plant.

• Nuclear Engineering and Technology
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• 제55권7호
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• pp.2489-2497
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• 2023

Co and Eu impurities in the SSCs are nuclides that dominantly influence the neutron-induced radioactive inventory in metal and concrete radwastes (radioactive wastes) during NPP decommission. The impurity concentrations provided by NUREG/CR-3474 were used for the practical range of Co and Eu impurity concentrations to be applied to the code calculations. Metal structures near the core were evaluated to be ILW (intermediate-level waste) for the whole range of Co impurity concentration, so the boundary line between ILW and LLW (low-level waste) has no change for the whole concentration range provided by NUREG/CR-3474. Also, the boundary line between VLLW (very low-level waste) and CW (clearance waste) in the concrete shield could alter a little depending on the Eu impurity concentration within the range provided by NUREG/CR-3474. From this work, it is found that the concentration of material impurities of SSCs gives no critical impact on determining radwaste levels.