• Journal of the Korean Recycled Construction Resources Institute
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• v.5 no.2
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• pp.168-176
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• 2017

This study, as a research for using crushed sand as a fine aggregate of concrete for nuclear structures, we improved the performance of impact crusher in the existing crushed sand production process and adjusted grain size to conform to ASTM C 33 The shape and grain size characteristics of a crushed sand were examined and concrete was prepared according to the substitution ratio of the sand to investigate the properties of fresh concrete and hardened concrete. The experimental results show that most of the concrete characteristics are equivalent to those of concrete using only heavy sand. However, when the substitution rate of steel sand exceeds 50%, the amount of air, compressive strength and tensile strength are somewhat reduced.

• Journal of the Korea institute for structural maintenance and inspection
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• v.8 no.4
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• pp.195-202
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• 2004

In this study, it was founded to make the optimal mixture for producing concrete which is self-compacting, yet, and generates low heat of hydration by using flyash, blast furnace slags and limestone powders as binders in addition to cement while using super-plasticizers and viscosity agents as admixture agents. The structural behaviors of the concrete produced with the selected mixture were compared with those of the concrete currently using for construction of nuclear power plants. The study shows that the blended high fluidity concrete including limestone is better in workability and durability than the concrete currently in use for nuclear power plants.

• Proceedings of the Korea Concrete Institute Conference
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• 2004.05a
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• pp.412-415
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• 2004

This study was performed to verify the behaviors of fiber Bragg grating (FBG) sensors attached to the containment structure in the nuclear power plant as a part of structural integrity test which demonstrates that the structural response of the non-prototype primary containment structure is within predicted limits plus tolerances when pressurized to $115\%$ of containment design pressure, and that the containment does not sustain any structural damage.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.10a
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• pp.778-783
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• 1997

원자력 발전소에서의 중대사고시, 고온의 노심 용융물이 원자로 공동으로 떨어지면 노심용융물과 콘크리트간의 반응(MCCI)에 의한 여러가지 현상으로 인해 격납용기의 건전성을 위협할 수 있다. 본 연구에서는 국내 영광원전 3, 4호기에 사용된 공동구조물 콘크리트와 고온용융물간의 반응특성을 실험적으로 살펴보았다. 실험은 유도가열로를 이용한 1차원 장기침식을 모사하기 위한 MEK-S1 실험이다. 실험에서는 유도로의 전원부족으로 용융풀을 형성하지 못하여 장기침식에는 실패하였다. 하지만 약 150$0^{\circ}C$의 고온 SUS 304에 의한 콘크리트의 침식을 확인할 수 있었다. 실험후 분해한 콘크리트 반응시편의 단면은 침식으로 인해 매우 불규칙한 모양을 나타내었으며, 최대침식 깊이는 24mm로 나타났다. 실험중에 발생한 가스의 성분분석 결과에서 H$_2$, $CO_2$, CO 및 $O_2$, $N_2$등의 가스가 발생된 것을 알 수 있었다.

• Proceedings of the Korea Concrete Institute Conference
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• 2003.11a
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• pp.136-139
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• 2003

The re-bar work in the construction of nuclear power plants is difficult, due to the large diameter and the congestion of reinforcements. The mechanical anchorage offers a potential solution for this problem. However, the requirements or the standards for the shape of anchor plate of mechanical anchor has not been clearly established up to now. In this paper, the required performance of the mechanical anchorage for large diameter reinforcements in nuclear power plants are proposed, and the anchor plates are designed through nonlinear finite element analysis. The diameters of anchor plate are determined to be $\sqrt{5}$ times of reinforcement diameter for longitudinal reinforcements and $\sqrt{10}$ for shear reinforcements. The thickness of anchor plates is optimized as 0.3-0.35 times of reinforcement diameter for longitudinal reinforcements and 0.5~0.56 times for shear reinforcements.