• 한국압력기기공학회 논문집
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• 제20권1호
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• pp.39-48
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• 2024

Research reactors are operated under ambient temperature and atmospheric pressure, which is much less severe conditions compared to those in typical nuclear power plants. Due to the high temperature, heat resistant materials such as austenite stainless steel should be used for the reactors in typical nuclear power plants. Whereas, as the effect of temperature is low for research reactors, materials with high resistance to neutron irradiation, such as zircaloy and beryllium, are used. Therefore, these conditions should be considered when performing integrity assessment for research reactors. In this study, a computational technique through finite element (FE) analysis was developed considering the operating conditions and materials of research reactor when conducting integrity assessment. Neutron irradiation analysis techniques using thermal expansion analysis were proposed to consider neutron irradiation growth and swelling in zirconium alloys and beryllium. A user subroutine program that can calculate the strain rate induced by neutron irradiation creep was developed for use in the commercial analysis program Abaqus. To validate the proposed technique and the user subroutine, FE analysis results were compared with hand-calculation results, and showed good agreement. Consequently, developed technique and user subroutine are suitable for evaluating structural integrity of research reactors.

• Corrosion Science and Technology
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• 제12권2호
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• pp.102-112
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• 2013

A very high-temperature gas reactor (VHTR) is one of the next generation nuclear reactors owing to its safety, high energy efficiency, and proliferation-resistance. Heat is transferred from the primary helium loop to the secondary helium loop through an intermediate heat exchanger (IHX). Under VHTR environment Alloy 617 is being considered a candidate Ni-based superalloy for the IHX of a VHTR, owing to its good creep resistance, phase stability and corrosion resistance at high temperature. In this study, high-temperature corrosion tests were carried out at 850 - $950^{\circ}C$ in air and impure helium environments. Alloy 617 specimens showed a parabolic oxidation behavior for all temperatures and environments. The activation energy for oxidation was 154 kJ/mol in helium environment, and 261 kJ/mol in an air environment. The scanning electron microscope (SEM) and energy-dispersive x-ray spectroscopy (EDS) results revealed that there were a Cr-rich surface oxide layer, Al-rich internal oxides and depletion of grain boundary carbide after corrosion test. The thickness and depths of degraded layers also showed a parabolic relationship with the time. A corrosion rate of $950^{\circ}C$ in impure helium was higher than that in an air environment, caused by difference in the outer oxide morphology.

• 한국주조공학회지
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• 제20권4호
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• pp.240-246
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• 2000

Surface layer properties such as composition, phase, hardness, and oxide layer condition are very important if the main failure mechanism of metals is wear. Generally, stable and dense oxide layers are known to decrease the wear rate of metals by prohibition of metallic junction occurred between bare metals. Addition of Si above 4 wt% to DCI(Ductile Cast Iron) is reported to enhance the significant oxidation resistance by forming the silicon-rich surface layer which inhibits further oxidation. And addition of up to 2 wt% Mo to high Si ductile iron produces significant increases in high temperature tensile strength, creep strength, thermal fatigue resistance and oxidation resistance. High pressure wear characteristics of unalloyed DCI(Ductile cast Iron), 4.46 wt% Si ductile iron, 4.3 wt% Si-0.52 wt% Mo ductile iron were investigated through unlubricated pin-on-disc wear test. Wear test was carried out at speed of 23m/min, under pressure of 3 MPa and 3.3 MPa. Wear surfaces of each specimen were observed by SEM to determine the wear mechanism under high pressure wear condition. Addition of Si 4.46 wt% severely deteriorated wear property of ductile iron compared to unalloyed DCI. But combined addition of Si 4.3 wt%andMo0.52wt%decreasedthefrictioncoefficient(${\mu}$)ofductileironsandremarkablydelayedthemild-severeweartransition.

• 한국지반공학회논문집
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• 제24권8호
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• pp.25-34
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• 2008

연약 지반의 거동 특성 평가를 위하여 전단파 속도와 전기저항을 측정할 수 있는 새로운 압밀셀을 개발하였다. 전단파의 발진과 수신을 위한 벤더엘리먼트는 압밀셀의 상 하부판 및 벽면에 설치하였다. 국부적인 간극비 변화를 평가하기 위하여 이중 쐐기 형식의 전기저항 탐침을 적용하였다. 벤더 엘리먼트와 전기저항 탐침은 나일론 재질의 스크류 안에 고정하였다. 나일론 재질의 스크류는 압밀셀과의 임피던스 차이로 인하여 압밀셀을 통한 파의 직접적 전달을 최소화하며, 고장난 벤더 엘리먼트와 전기저항 탐침을 쉽게 교환하게 해준다. 전기저항-대수 시간 곡선의 기울기 및 전단파 속도의 변화로부터 일차 압밀 시간을 평가하였다. 교란 효과가 적을 경우, 입자 배열은 전단파 속도에 영향을 미치며 이로부터 흙의 고유 이방성을 평가할 수 있었다. 압밀 실험동안 침하량으로 산정한 간극비와 전기저항으로부터 계산된 간극비는 거의 유사한 것으로 나타났다. 본 연구는 전단퐈 속도와 전기저항이 일차 압밀, 고유 이방성, 간극비 등 연약 지반의 압밀 특성 파악을 위한 보완적인 정보를 제공해 줌을 보여준다.

• 한국지반공학회논문집
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• 제28권7호
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• pp.55-65
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• 2012

지오그리드의 장기허용강도를 산출할 때 사용되는 총 감소계수는 내시공성 감소계수($RF_{ID}$), 내화학성 감소계수($RF_D$), 크리프 감소계수($RF_{CR}$) 등이 적용된다. 지오그리드의 단기인장강도에 대한 감소계수를 고려한 허용인장강도 산출 모델의 경우 감소계수들 사이의 상호 작용력을 고려하지 않는 한계를 가지고 있다. 접점강도는 인장강도와 마찬가지로 시공 시 손상이나 화학적 분해에 의하여 감소하게 된다. 기존의 단일접점강도 시험 방법은 치수효과를 고려할 수 없기에 결과의 편차가 큰 시공 시 손상된 시험편의 접점강도를 측정하는데 적합하지 않다. 또한 시공 시 손상에 의한 전단강도 변화에 대한 연구도 전혀 이루어지지 않은 실정이다. 따라서 본 연구에서는 다양한 조건을 고려하여 지오그리드의 장기성능에 영향을 미치는 감소계수들을 재평가하고 감소계수 사이의 상호 작용을 고려하여 정확한 장기허용강도를 구하려고 한다. 내시공성 시험과 내화학성 시험 후 크리프 시험결과 총 감소계수는 GRI GG-4 시험값보다 작게 나타났다. 내시공성 시험과 내화학성 시험 후 접점강도의 감소계수는 인장강도 감소계수보다 더 작게 나타났다. 내시공성 시험후 전단강도 차이가 나타나지 않거나 증가함을 나타내었다.

• 공업화학
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• 제20권4호
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• pp.459-463
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• 2009

본 논문에서는 poly(vinyl acetate-co-ethylene) (VAE) 에멀젼에 가소제로 많이 사용되는 di-butyl phthalate (DBP)를 혼합하여 가소제 함량에 따른 물성 변화를 고찰하였다. 시차주사열량계(Differential Scanning Calorimeter) 측정으로부터 건조한 필름의 유리전이온도($T_g$)를 측정한 결과,가소제 함량의 증가에 따라, $T_g$는 감소하는 경향을 나타내었고 반면에 에멀젼의 점도는 가소제 함량의 증가와 더불어 증가하였다. 이러한 결과는 건조한 필름상태에서 가소제는 고분자사슬의 상호작용을 방해하여 $T_g$를 감소시키며 에멀젼 상에서는 가소제가 에멀젼 입자 내로 침투하여 swelling시킴으로써 입자크기가 증가하고 점도를 상승키는 것으로 나타났다. 기계적 물성은 가소제의 함량이 증가할수록 저하되었으나 내수성은 증가되는 결과를 얻었다.

• 대한기계학회논문집A
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• 제27권8호
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• pp.1398-1408
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• 2003

Tensile and LCF(low cycle fatigue) tests were carried out in air at wide temperature range 20$^{\circ}C$-750$^{\circ}C$ and strain rates of 1${\times}$10$\^$-4//s-1${\times}$10$\^$-2/ to ascertain the influence of strain rate on tensile and LCF properties of prior cold worked 316L stainless steel, especially focused on the DSA(dynamic strain aging) regime. Dynamic strain aging induced the change of tensile properties such as strength and ductility in the temperature region 250$^{\circ}C$-600$^{\circ}C$ and this temperature region well coincided with the negative strain rate sensitivity regime. Cyclic stress response at all test conditions was characterized by the initial hardening during a few cycles, followed by gradual softening until final failure. Temperature and strain rate dependence on cyclic softening behavior appears to result from the change of the cyclic plastic deformation mechanism and DSA effect. The DSA regimes between tensile and LCF loading conditions in terms of the negative strain rate sensitivity were well consistent with each other. The drastic reduction in fatigue resistance at elevated temperature was observed, and it was attributed to the effects of oxidation, creep and dynamic strain aging or interactions among them. Especially, in the DSA regime, dynamic strain aging accelerated the reduction of fatigue resistance by enhancing crack initiation and propagation.

• 한국재료학회지
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• 제5권7호
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• pp.869-879
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• 1995

TiAi intermetallic compound has been extensively studied for possible high temperature structural applications because of its high specific strength at high temperature, high creep resistance, and good oxidation resistance at elevated temperatures. In addition to its good properties, an economic manufacturing routes should be developed for this material to be used more extensively. One of the promising route in manufacturing TiAl intermetallics is the Self-propagating High-temperature Synthesis (SHS) method. Thus in this study, an attempt was made to study the mechanism of the SHS process in TiAl synthesis. The composition of the sample was Ti-(45, 50, 53)at% Al and the microstuctures of the products were analyzed using optical microscope and scanning electron microscope. When the phases formed at the main SHS reaction of whicyh combustion temperature is higher than the melting temperature of aluminum were identified as TiAl and Ti$_3$Al ; Ti$_3$Al cores surrounded by TiAl phase. In order to increase the combustion temperature, carbon was added 5 and 10at.%. When the carbon content was 10at.%, the heat of the reaction was large enough to melt the phase formed and that is consistent with the theoretical calculation results of the adiabatic temperature. The combution temperatue, which was measured by a computer data acquisition system, increased with the carbon content. The phases formed from the reaction involving the carbon added were indentified as TiAl and Ti$_2$AlC using XRD. The vickers hardness of the reaction product increased with the carbon content.

• 한국분말야금학회:학술대회논문집
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• 한국분말야금학회 1996년도 추계학술강연 및 발표대회 강연 및 발표논문 초록집
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• pp.6-6
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• 1996

Ceramic based nanocomposite, in which nano-sized ceramics and metals were dispersed within matrix grains and/or at grain boundaries, were successfully fabricated in the ceramic/cerarnic and ceramic/metal composite systems such as $Al_2O_3$/SiC, $Al_2O_3$/$Si_3N_4$, MgO/SiC, mullite/SiC, $Si_3N_4/SiC, $Si_3N_4$/B, $Al_2O_3$/W, $Al_2O_3$/Mo, $Al_2O_3$/Ni and $ZrO_2$/Mo systems. In these systems, the ceramiclceramic composites were fabricated from homogeneously mixed powders, powders with thin coatings of the second phases and amorphous precursor composite powders by usual powder metallurgical methods. The ceramiclmetal nanocomposites were prepared by combination of H2 reduction of metal oxides in the early stage of sinterings and usual powder metallurgical processes. The transmission electron microscopic observation for the $Al_2O_3$/SiC nanocomposite indicated that the second phases less than 70nm were mainly located within matrix grains and the larger particles were dispersed at the grain boundaries. The similar observation was also identified for other cerarnic/ceramic and ceramiclmetal nanocornposites. The striking findings in these nanocomposites were that mechanical properties were significantly improved by the nano-sized dispersion from 5 to 10 vol% even at high temperatures. For example, the improvement in hcture strength by 2 to 5 times and in creep resistance by 2 to 4 orders was observed not only for the ceramidceramic nanocomposites but also for the ceramiclmetal nanocomposites with only 5~01%se cond phase. The newly developed silicon nitride/boron nitride nanocomposites, in which nano-sized hexagonal BN particulates with low Young's modulus and fracture strength were dispersed mainly within matrix grains, gave also the strong improvement in fracture strength and thermal shock fracture resistance. In presentation, the process-rnicro/nanostructure-properties relationship will be presented in detail. The special emphasis will be placed on the understanding of the roles of nano-sized dispersions on mechanical properties.

• Nuclear Engineering and Technology
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• 제39권3호
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• pp.193-206
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• 2007

The Korea Atomic Energy Research Institute has developed an advanced fast reactor concept, KALIMER-600, which satisfies the Generation IV reactor design goals of sustainability, economics, safety, and proliferation resistance. The concept enables an efficient utilization of uranium resources and a reduction of the radioactive waste. The core design has been developed with a strong emphasis on proliferation resistance by adopting a single enrichment fuel without blanket assemblies. In addition, a passive residual heat removal system, shortened intermediate heat-transport system piping and seismic isolation have been realized in the reactor system design as enhancements to its safety and economics. The inherent safety characteristics of the KALIMER-600 design have been confirmed by a safety analysis of its bounding events. Research on important thermal-hydraulic phenomena and sensing technologies were performed to support the design study. The integrity of the reactor head against creep fatigue was confirmed using a CFD method, and a model for density-wave instability in a helical-coiled steam generator was developed. Gas entrainment on an agitating pool surface was investigated and an experimental correlation on a critical entrainment condition was obtained. An experimental study on sodium-water reactions was also performed to validate the developed SELPSTA code, which predicts the data accurately. An acoustic leak detection method utilizing a neural network and signal processing units were developed and applied successfully for the detection of a signal up to a noise level of -20 dB. Waveguide sensor visualization technology is being developed to inspect the reactor internals and fuel subassemblies. These research and developmental efforts contribute significantly to enhance the safety, economics, and efficiency of the KALIMER-600 design concept.