The concrete structure of a nuclear power plant is a major safety structure that performs shielding functions to block radioactive materials and radiation, heat removal, and isolation functions. Therefore, concrete structures of nuclear power plants must prove structural safety from immediately after construction to dismantling, and a representative method for this is to investigate compressive strength. The compressive strength and specimen standards of concrete structures are specified in ASTM C 42/C 42M, and samples must be obtained through core drilling in order to collect samples according to this standard. However, commercial equipment requires anchor installation work causes radiation dust generation. Even commercial products have developed equipment that does not require anchor installation work, but it can only be applied to flat walls and cannot be applied to curved walls such as bioshields. To solve this problem, a method of fixing to the scaffolding pipe was designed. The equipment developed based on this method fundamentally blocks the generation of radioactive dust. The vertical position can be adjusted using guide shafts and jack screws, and the horizontal position can be adjusted using scaffolding clamps. In addition, the distance between the installation location and the wall can be adjusted by adjusting the scaffolding clamp location of the device. Lastly, it can be rotated to the left and right, so that even on a curved wall, the sampling position can be performed perpendicular to the wall. Core drills that take specimens for measuring compressive strength use the wet type. Core drilling by wet type in radioactively contaminated concrete leads to the disposal of sludge as radioactive waste. Water supplied during core drilling is scattered in all directions by the rotation of the core drill bit, which causes radiation exposure to workers, so measures must be taken to ensure that the water does not splash and gather in one place. Nileplant Co., Ltd. has developed a sludge collection device that can be used with a core drilling device. It can be inserted into a 4-inch core drill bit to meet the specimen regulations of ASTM C 42/C 42M, and nylon resin was used as a material to withstand friction with water, and the wall of the drainage part was thickened to increase durability. Based on these results, it is expected to be able to work more quickly and safely when collecting core drilling samples of radioactively contaminated concrete or radiation and concrete.

A literature review on the effects of high temperature and radiation on radiation shielding concrete in Spent Fuel Dry Storage is presented in this study with a focus on concrete degradation. The general threshold is 95℃ for preventing long-term degradation from high temperature, and it is suggested that the temperature gradient should be less than 60℃ to avoid crack generation in concrete structures. The amount of damage depends on the characteristics of the concrete mixture, and increases with the temperature and exposure time. The tensile strength of concrete is more susceptible than the compressive strength to degradation due to high temperature. Nuclear heating from radiation can be neglected under an incident energy flux density of 1010 MeV·cm-2·s-1. Neutron radiation of >1019 n·cm-2 or an integrated dose of gamma radiation exceeding 1010 rads can cause a reduction in the compressive and tensile strengths and the elastic moduli. When concrete is highly irradiated, changes in the mechanical properties are primarily caused by variation in water content resulting from high temperature, volume expansion, and crack generation. It is necessary to fully utilize previous research for effective technology development and licensing of a Korean dry storage system. This study can serve as important baseline data for developing domestic technology with regard to concrete casks of an SF (Spent Fuel) dry storage system.

본 연구에서는 확산에 의해 발생하는 시멘트 방벽의 변질 과정을 반응성용질이동 모델링을 통해 장기간 동안 예측하고자 하였다. 모델링 결과 50,000년 후 시멘트의 변질은 30cm까지 진행되었다. pH는 13.0에서 11.86까지 감소하였으며 이는 알칼리 이온의 감소, 포틀랜다이트(portlandite)와 CSH (Calcium Silicale Hydrate)광물의 용해/침전반응에 의해 결정되고 있었다. 공극률 또한 portlandite와 의 용해에 의해 가장 큰 영향을 받고 있었으며 최고 약 0.3 점도 증가하였다. 우라늄의 용해도 역시 증가하고 있었으며 이는 pe의 증가에 기인하고 있었다. 본 연구 결과는 장기간의 시멘트 변질이 pH, pe, 공극률을 변화시킴으로서 핵종의 이동을 증가시킬 수 있음을 보여주고 있다.

This study provides a simple introduction to photo-catalyst technology to self-clean the organic dirts and degrade the air pollution in urban environment. Moreover, it shows the spray coating technique was applied to effective coating on the surface of concrete specimen by using as-developed integral photocatalyst solution. In order to examine photo-catalytic activity and degradation effectiveness on the surface of the concrete specimen, the UV-LED lamp was used as a light source to activate the photo-catalysis. Methyl-orange dye was used as an indicating method to speculate the photo-catalytic reaction and UV-VIS spectrometer to determine the molar content of the organic dye.

Eight small scale circular reinforced concrete columns were tested under cyclic lateral load with 4.5 aspect ratio. The test variables are longitudinal steel ratio, transverse steel ratio, and axial load ratio. Eight flexurally dominated columns were tested. In all specimens, initial flexural-shear cracks occurred at 1.5% drift ratio. The multiple flexural-shear crack width and length gradually increased until the final stage. The angles of the major inclined cracks measured from the vertical column axis ranged between 40 and 48 degrees. In particular, this study focused on assessing transverse reinforcement contribution to the column shear strength. Transverse reinforcement contribution measured during test. Each three components of transverse reinforcement contribution, axial force contribution and concrete contribution were investigated and compared.

콘크리트는 장기수명이 요구되는 구조물에 적합한 건설재료로 내구성이 우수하지만 장기간 지하수에 노출되어 발생하는 칼슘용출 현상에 대한 이해 및 이에 따른 RC 부재의 휨 거동 특성을 평가할 필요가 있다. 실험결과에 따르면, 광물질 혼화재는 RC 부재의 장기강도 개선에 효과적이지만, 칼슘용출이 발생하면 RC 부재의 항복하중 및 휨 강성이 감소하고 중립축깊이와 처짐량이 증가하는 것으로 나타났다. 따라서 칼슘용출에 의한 열화는 RC 부재의 성능 저하를 유발하므로 칼슘용출 환경에 노출되는 지하구조물에 광물질 혼화재가 적용될 경우에는, 광물질 혼화재 종류에 따른 최적 혼입 비율이 마련되어야할 것으로 사료된다.

철근콘크리트 교량에 대한 대부분의 내진설계기준들은 전체 교량 시스템의 붕괴를 방지하기 위한 성능보장설계를 암시적 또는 명시적으로 적용하고 있다. 이러한 개념 및 규정들을 명시하는 이유는 교량 전체 시스템에 설계지진하중이 작용하는 동안 철근콘크리트 교각들 이 완전한 소성회전성능을 발휘할 때까지 구조적인 다른 구성요소들의 취성적인 파괴를 방지하기 위함이다. 이를 위해 철근콘크리트 교량에 대한 내진설계기준들에서는 취성적인 전단파괴를 피하도록 규정하고 있다. 성능보장의 중요한 요소 중의 하나가 교각의 연성거동을 보장하기 위한 전단강도가 충분히 확보되어야 하고 신뢰할 수 있어야 한다. 실험체 8개에 대하여 실험을 수행하였으며 모든 실험체에서 변위비 1.5%에 서 다수의 휨-전단 균열이 발생되었고 최종단계까지 균열폭이 증가되었고 균열이 진전되었다. 휨-전단 균열의 각도는 부재 축과 42°~ 48°의 범 위로 계측되었다. 본 연구에서는 실험에서 계측된 횡방향철근이 부담하는 전단강도에 대한 분석을 중심으로 하였다. 횡방향철근이 부담하는 전단강도, 축력 작용에 의한 전단강도, 콘크리트에 의한 전단강도 등 3요소에 대해 분석하였고 비교하였다. 실험체들의 콘크리트 응력은 도로 교설계기준의 응력한계를 초과하였다.

Concrete has been recognized as a material which is resistant to the high temperature, but chemicophysical property of concrete is changed by the high temperature. So, mechanical properties of concrete may be reduced. Therefore, concrete is evaluated mechanical properties for safety inspection. However, research of ultrasonic pulse method is not much. Therefore, the purpose of this study is to Non-Destructive Test of 30, 70, 110MPa concrete exposed high temperature using ultrasonic pulse velocity.

Concrete has been recognized as a material which is resistant to the high temperature, but chemicophysical property of concrete is changed by the high temperature. So, mechanical properties of concrete may be reduced. Therefore, concrete is evaluated mechanical properties for safety inspection. However, research of ultrasonic pulse method is not much. Therefore, the purpose of this study is to Non-Destructive Test of 30, 70, 110MPa concrete exposed high temperature using ultrasonic pulse velocity.

다양한 열화 인자에 의해 저감된 콘크리트의 내구성은 구조물의 구조적 성능과 사용 수명에 부정적인 영향을 미치게 되며 콘크리트 연구 분야 중에서도 매우 중요하고 매력적인 주제라고 할 수 있다. 이러한 이유로 콘크리트의 내구성과 관련된 많은 연구들이 발표되었으나 물리-화학적 열화에 기인하는 콘크리트의 본질적인 물성 변화에 주된 초점이 맞춰져 왔으며, 콘크리트 내구성과 구조물의 구조적 성능 사이의 관계 정립은 아직 미흡한 실정이다. 본 연구에서는 콘크리트의 강도 감소에 원인이 되는 칼슘 용출 열화를 적용하였으며, 열화 정도에 따른 구조적 거동을 평가하기 위하여 열화 손상을 입은 콘크리트 부재의 압축 및 휨 거동 실험을 수행하고 그 결과를 비선형 유한요소해석 결과와 비교 분석하였다. 연구 결과에 따르면 칼슘 용출 열화는 콘크리트의 압축 강도를 저하시키며, 열화가 진행됨에 따라 취성 거동에서 연성 거동으로 변화되는 경향을 나타냈다. 또한 열화에 의한 압축 영역의 손상 정도가 심화될수록 RC 부재의 내하력과 강성은 저하되었으며, 이러한 구조적 거동은 ABAQUS의 CDP 모델을 사용한 비선형 유한요소해석의 결과와도 비교적 잘 일치하였다.

The strength, water permeability, and photo-degradation efficiency of NOx of porous concrete with a new concept were studied in this paper. The porous concrete was comprised of coarse aggregate of maximum size 40 mm, cement, silica fume, water and air-entraining(AE) water reducing agent. The strength of porous concrete was strongly related to its matrix proportion and compaction energy. An experimental test was carried out to study the parameters of cement proportions and silica fume content for pavement applications of porous concrete which were paving a footpath, a bikeway, a parking lot, and a driveway. The regressed equations of relationships between compressive strength and flexural strength, and coefficient permeability and void ratios were indicated as y=7.69x+71.74 and y=0.42e0.28x. A method of making an air purification-functioning road, which was spraying a mixture of a photocatalyst, cement, and water onto the surface of the road, was suggested.