• 한국재료학회지
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• 제31권5호
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• pp.255-263
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• 2021

P91 steel has been a highly researched material because of its applicability for high-temperature applications. Considerable efforts have been made to produce experimental creep data and develop models for creep life prediction. As creep tests are expensive and difficult to conduct, it is vital to develop authenticated empirical methods from experimental results that can be utilized for better understanding of creep behavior and can be incorporated into computational models for reliable prediction of creep life. In this research, a series of creep rupture tests are performed on the P91 specimens within a stress range of 155 MPa to 200 MPa and temperature range of 640 ℃ (913 K) to 675 ℃ (948 K). The microstructure, hardness, and fracture surfaces of the specimens are investigated. To analyze the results of the creep rupture tests at a macro level, a parameter called creep work density is derived. Then, the relationships between various creep parameters such as strain, strain rate, time to rupture, creep damage tolerance factor, and creep work density are investigated, and various empirical equations are obtained.

• 한국산림과학회지
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• 제113권1호
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• pp.14-30
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• 2024

본 연구는 한국의 울주군에서 발생한 땅밀림지의 지질, 지형, 유효 토심, 토양경도, 전기비저항탐사, 지반조사를 통해 땅밀림 위험지 특성을 파악하여 땅밀림에 의한 인적, 물적 피해를 완화하기 위한 기초자료를 제공하기 위해 실시하였다. 이 지역은 2022년 도로 확장공사의 영향으로 땅밀림이 발생하였는데, 하층식생이 크게 발달하지 않은 경사지로 상단부는 강우 시 집수가 잘 되는 요형 지형으로 나타났다. 땅밀림지의 주 구성 암석은 셰일, 사암, 역암으로 구성되어 있으며 땅밀림지의 토양은 대조구의 토양보다 점토함량이 약 3.6배 많은 것으로 분석되었으며, 모래와 점토가 많고, 실트가 적은 결과로 전형적인 땅밀림 토양으로 나타났으며, 전기비저항 탐사결과 저비저항이상대가 나타나 지하수대가 형성되는 것으로 나타났다. 토양 경도는 대조구보다 땅밀림지가 낮았으며, 땅밀림지의 평균토심은 30.4 cm로 대조구 24.7 cm보다 깊은 붕적토 지역이었다. 이러한 땅밀림의 특징을 파악하여 효과적인 선제적 대응 체계와 모니터링 시스템 구축이 필요하다.

• Tribology and Lubricants
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• 제35권1호
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• pp.24-29
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• 2019

In this work we investigated the friction and wear characteristics of a magnesium alloy, which has been receiving much attention as a light metal in industrial applications such as automobiles and aerospace. Magnesium is one of the lightest structural material that has high specific strength, lightweight, low density and good formability. However, current issue of using magnesium alloy is that magnesium has weakness against temperature. As the temperature increases, magnesium undergoes poor creep resistance and ease of softening, and therefore, its mechanical strength decreases sharply. To solve this issue, a new type of magnesium alloy that retains high strength at high temperature has been proposed. The tribological behavior of this alloy was investigated using a tribotester with reciprocating motion and heating plate. A stainless steel ball was used as a counter surface. Results showed that extrusion process has similar wear behavior to the commonly used casting process but retains good mechanical strength and durability. The presence of an alloying element enhanced the wear properties especially in high temperature. This study is expected to be utilized as fundamental data for the replacement of high density materials currently used in mechanical industries to a much lighter and durable heat-resistant materials.

• 콘크리트학회논문집
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• 제13권6호
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• pp.568-574
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• 2001

콘크리트 시험편에 대한 삼점휨실험을 실시하여 여러 실험에 대해 측정된 반응의 평균값을 계산하곤 계산된 평균거동으로부터 삼점휨 시험편이 완전히 파손될 때까지 연속적으로 성장하는 균열에 대한 파괴거동이 분석되었다. 이 연구에서 사용된 실험변수는 25.4mm와 6.4mm의 초기균열길이 그리고 2000sec와 20sec의 실험기간이며, 초기균열길이는 파괴진행대(FPZ) 크기의 영향과 시험편의 기하학적 특성 및 경계조건에 대한 영향을 분석하기 위한 것이다. 실험기간은 초기 크리프(creep)의 영향을 위해 설정되었으나, 이 연구의 하중점-변위 속도에서는 심각한 영향이 관측되지 않았다. 여러 실험의 평균 외부일로부터 평균하중이 계산되었으며, 변형률 게이지를 사용하여 평균 균열길이를 측정하였다. 최대하중 이전의 저항곡선은 파괴진행대의 크기에 대해 유사한 값을 보였다. 그러나 최대하중 직후에는 초기균열의 크기에 관계없이 0.088~0.154mm의 하중점-변위에서 88mm의 불안정 균열성장이 발생되었으며, 평균 파괴에너지율 $G_{F}$$^{ave}$ = 115N/m은 이 불안정 균열성장 동안에 발생되었다. 균열길이 111mm에서 완전한 파괴진행대가 형성되었고, 25.4mm와 6.4mm의 초기균열길이에 대해 파괴진행대의 크기는 각각 86mm와 105mm이었다. 완전한 파괴진행대의 형성이후 저항곡선의 평균 파괴에너지율은 25.4mm와 6.4mm의 초기균열길이에 대해 각각 229N/m로 284N/m로 $G_{F}$$^{ave}$의 두 배 이상이었다.이었다.이었다.

• 한국재료학회지
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• 제4권3호
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• pp.349-356
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• 1994

재료의고온소성변형과 수명예측 및 수명향상을 위하여 재료의 변형기구를 규명하는 것이 매우 중요하다. 이를 위하여 전위환모델이 자주 사용되며, 현재 실험적인 결과를 토대로 한 두개의 중요한 전위환모델로서, Orlova등고 Mills등이 제시한 모델들이 있다. 이들은 모두AI-5.5at.%MG을 사용하였으나 상호 상반된 전위환모델을 설명하고 있다. 그러므로 본 연구에서는 상반된 전위환 모델을 확인하기 위하여 AI-5.5at.%MG을 사용하여 573K의 약 30MPa에서 $\varepsilon$=0.03까지 크\ulcorner시험을 하고, 이러한 크\ulcorner시험후 이어서 각각 약 15,10 및 oMPa의 응력감소 시험도 수행하였으며, 동시에 응력감소 시험 전과 후의 전위구조를 관찰하여 전위환모델을 고찰하였다.

• Nuclear Engineering and Technology
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• 제39권5호
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• pp.603-616
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• 2007

Roy Huddle, having invented the coated particle in Harwell 1957, stated in the early 1970s that we know now everything about particles and coatings and should be going over to deal with other problems. This was on the occasion of the Dragon fuel performance information meeting London 1973: How wrong a genius be! It took until 1978 that really good particles were made in Germany, then during the Japanese HTTR production in the 1990s and finally the Chinese 2000-2001 campaign for HTR-10. Here, we present a review of history and present status. Today, good fuel is measured by different standards from the seventies: where $9*10^{-4}$ initial free heavy metal fraction was typical for early AVR carbide fuel and $3*10^{-4}$ initial free heavy metal fraction was acceptable for oxide fuel in THTR, we insist on values more than an order of magnitude below this value today. Half a percent of particle failure at the end-of-irradiation, another ancient standard, is not even acceptable today, even for the most severe accidents. While legislation and licensing has not changed, one of the reasons we insist on these improvements is the preference for passive systems rather than active controls of earlier times. After renewed HTGR interest, we are reporting about the start of new or reactivated coated particle work in several parts of the world, considering the aspects of designs/ traditional and new materials, manufacturing technologies/ quality control quality assurance, irradiation and accident performance, modeling and performance predictions, and fuel cycle aspects and spent fuel treatment. In very general terms, the coated particle should be strong, reliable, retentive, and affordable. These properties have to be quantified and will be eventually optimized for a specific application system. Results obtained so far indicate that the same particle can be used for steam cycle applications with $700-750^{\circ}C$ helium coolant gas exit, for gas turbine applications at $850-900^{\circ}C$ and for process heat/hydrogen generation applications with $950^{\circ}C$ outlet temperatures. There is a clear set of standards for modem high quality fuel in terms of low levels of heavy metal contamination, manufacture-induced particle defects during fuel body and fuel element making, irradiation/accident induced particle failures and limits on fission product release from intact particles. While gas-cooled reactor design is still open-ended with blocks for the prismatic and spherical fuel elements for the pebble-bed design, there is near worldwide agreement on high quality fuel: a $500{\mu}m$ diameter $UO_2$ kernel of 10% enrichment is surrounded by a $100{\mu}m$ thick sacrificial buffer layer to be followed by a dense inner pyrocarbon layer, a high quality silicon carbide layer of $35{\mu}m$ thickness and theoretical density and another outer pyrocarbon layer. Good performance has been demonstrated both under operational and under accident conditions, i.e. to 10% FIMA and maximum $1600^{\circ}C$ afterwards. And it is the wide-ranging demonstration experience that makes this particle superior. Recommendations are made for further work: 1. Generation of data for presently manufactured materials, e.g. SiC strength and strength distribution, PyC creep and shrinkage and many more material data sets. 2. Renewed start of irradiation and accident testing of modem coated particle fuel. 3. Analysis of existing and newly created data with a view to demonstrate satisfactory performance at burnups beyond 10% FIMA and complete fission product retention even in accidents that go beyond $1600^{\circ}C$ for a short period of time. This work should proceed at both national and international level.