• Journal of Welding and Joining
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• 제7권3호
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• pp.28-35
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• 1989

It was reported that the toughness for welded region was influenced by various factors such as the gradient for prior austenite grain size, the variation of microhardness and the characteristic microstructure depending on distance from the fusion boundary. Therefore, in order to evaluate the fracture strength of the weldment in which the microstructures change continuously, it is important to assess the peculiar strength of each microstructure in welded region. It was known that the small punch(SP) test technique which was originally developed to study the irradiation damage effect for the structures of nuclear power plant was also useful to investigate the strength evaluating of nonhomogeneous materials. In this paper, by means of a small punch test technique the possibility of evaluating strength of parent and welded region in SS41 and SM53B steels was investigated. The obtained results are summerized as follows: 1) The small punch test which showed markedly the ductile-brittle transition behavior in this experiment may be applied to evaluation for the fracture strength of welded region. 2) It was shown that the ductile-brittle regime lied in Region III(plastic membrane stretching region) of the flow characteristics observed in SP test. 3) The SP test technique which shows a more precipitous energy change transition behavior than the other test technique is able to estimate the more precise transition temperature. 4) It could be seen that in comparision with the structure of parent the structure of weld HAZ in SS41 steel was improved while it in SM53B steel was deteriorated.

• 한국분말야금학회:학술대회논문집
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• 한국분말야금학회 2006년도 Extended Abstracts of 2006 POWDER METALLURGY World Congress Part2
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• pp.1161-1162
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• 2006

In order to overcome the recrystallization embrittlement and irradiation embrittlement of Mo, which are major problems for its fusion applications, internally nitrided Mo alloys were prepared by a novel multi-step internal nitriding. Neutron irradiation was performed in the Japan Material Testing Reactor (JMTR). After irradiation, nitrided Mo alloys exhibited $\iota$ ower ductile-brittle transition temperature than irradiated TZM. These results suggested that multi-step internal nitriding was effective to the improvement in the embrittlement by irradiation. Transmission electron microscope observation revealed that TiN particles precipitated by nitriding acted as a sink for irradiation-induced defects.

• 대한기계학회논문집A
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• 제24권6호
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• pp.1398-1407
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• 2000

The structural steels of power plant show the decrease of mechanical properties due to degradation such as temper embrittlement, creep damage and softening during long-term operation at high temper ature. The typical causes of material degradation damage are the creation and coarsening of carbides(M23C6, M6C) and the segregation of impurities(P, Sb and Sn) to grain boundary. It is also well known that material degradation induces the cleavage fracture and increases the ductile-brittle transition temperature of steels. So, it is very important to evaluate degradation damage to secure the reliable and efficient service condition and to prevent brittle failure in service. However, it would not be appropriate to sample a large test piece from in-service components. Therefore, it is necessary to develop a couple of new approaches to the non-destructive estimation technique which may be applicable to assessing the material degradation of the components with not to influence their essential strength. The purpose of this study is to propose and establish a new electrochemical technique for non-destructive evaluation of material degradation damage for Cr-Mo steels which is widely used in the high temperature structural components. And the electrochemical anodic polarization test results are compared with those of semi-nondestructive SP test.

• 한국재료학회지
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• 제11권6호
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• pp.508-511
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• 2001

사파이어 단결정의 취성-연성전이에 대한 실험을 행하였다. 사파이어 단결정의 취성-연성전이온도는 변형율 3.3$\times$ $10^{-5}$/sec에서 $1000\pm$$25^{\circ}C$ 그리고 변형률 3.3$\times$$10^{-5}$/sec에서는 1100$\pm$26$^{\circ}C$이었다. 취성-연성전이모델을 이용하여 Prism Plane slip {1120} <1100> 전위속도의 활성화에너지를 계산하였으며, 그 결과 활성화에너지는 4.6$\pm$2.3eV의 범위를 가졌다. 이 활성화에너지는 에치-퍼트법을 이용하여 전위속도측정으로부터 구한 결과치 3.8eV와 유사하였다.

• Nuclear Engineering and Technology
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• 제34권6호
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• pp.574-585
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• 2002

The microstructural characteristics and its related mechanical properties of RPV cladding have been investigated using small punch (SP) tests. SA508 Cl.3 RPV steel plates were overlay cladded with the type ER309L welding consumables by submerged arc welding process. Although the RPV clad material had a small portion of 5 ferrite phase, it still showed the ductile to brittle transition behavior The transition temperature was determined by the SP test and it depended on the content of $\sigma$ phase, specimen size, and determination methods. The fracture appearance of SP specimen was changed from circumferential to radial cracking as test temperature became low, and below the transition temperature region, ER309L cladding usually fractured along the 6 ferrite by the low temperature failure of ferrite phase.

• Elastomers and Composites
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• 제39권2호
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• pp.142-152
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• 2004

서로 다른 두 종류의 폴리스타일렌(PS)을 injection 기계를 이용하여 인장 시편을 만들고, 온도와 인장 속도에 따른 crazing 거동 특성을 연구하기 위하여 다양한 시험을 하였다. 기계적물성은 craze 형성뿐만 아니라 다양한 시험 변수에 의해 영향을 받으며, brittle-ductile transition 이하의 온도에서의 인장 응력 및 최대 신율은 분자량, 인장 속도의 증가 및 온도의 감소에 따라 증가하며 craze의 수와 평균 길이 또한 증가한다. Crazing 응력도 동일한 형태로 증가함을 보여준다. 그러나, 이러한 특성은 인장 강도에 미치는 영향과 비교했을 때 보다 의존도는 상대적으로 낮다. Craze 형성과 성장에 필요한 시간으로 설명할 수 있는 crazing 응력과 인장 응력간의 차이는 분자량, 인장 속도에 따라 비례적으로 그리고, 온도가 감소함에 따라 증가함을 보여 준다. Crazing 은 ${\beta}$-relaxation 온도 근처에서 활성화된다. 이 온도에서는 crazing 응력이 급격하게 감소함을 나타낸다. 인장 평가시 craze 밀도가 적용된 응력에 따라 기하 급수적으로 증가되는데, 개시 단계에서는 craze는 서서히 형성되며, 일단 일정한 수만큼의 craze가 형성이 되면 craze 밀도가 급속도로 증가했다.

• 한국가스학회지
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• 제2권4호
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• pp.42-46
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• 1998

소형 시험편 기술은 최소량의 재료를 사용하여 그 재료의 물리적인 거동을 특성화할 수 있기 때문에 산업설비로부터 많은 재료를 수집할 수 없는 경우에 유용한 방법이다. 본 연구에서 사용한 재료는 화력발전소 터빈로터 소재로 많이 사용되고 있는 1Cr-1Mo-0.25V강이었으며, $^630{\circ}C$에서 등온열화처리하여 5종류의 가속 열화 모사재를 만들었다. 충격시험에는 표준 시험편과 소형 시험편이 사용되었으며, 일부 소형 시험편에 소성 구속을 증가시키기 위해 측면흠을 만들어 넣었다. 표준 시험편과 소형 시험편의 충격특성을 비교하였으며 크기효과를 고찰하였고, 소형 시험편의 연성취성천이온도와 표준 시험편의 연성취성천이온도와의 상관관계를 만들었다. 따라서 소형 시험편의 충격시험결과로부터 표준 시험편의 충격특성을 추정하는 것이 가능하게 되었다.

• 한국주조공학회지
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• 제2권2호
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• pp.2-9
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• 1982

This paper is concerned with the improvement of impact and tensile Properties of spheroidal graphite cast iron of the following duplex matricess which were heat treated in the eutectic transformation temperature range (that is, $({\alpha}+{\gamma})$ coexisting range) ; ferrite-martensite, ferrite-bainite and ferrite-pearlite. The absorbed energy and maximum load was measured by recording the load-deflection curve with instrumented Charpy impact testing machine in the temperature range from $+100^{\circ}C$ to $-196^{\circ}C$. It was found the ferrite-bainite duplex matrix showed the highest toughness among the above matrices in the room temperature and the low temperature range. Comparison of this matrix to ferrite-pearlite matrix(that is, as cast) showed a lowering of $27^{\circ}C$ in the nil-ductility transition temperature (NDT) and a lowering of $40^{\circ}C$ in the ductile-brittle transition temperature (TrE), Which seems to result from the finner dimple pattern observed using miorofractography.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2000년도 추계학술대회논문집A
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• pp.105-110
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• 2000

The Micromechanics test is new test method which uses comparatively smaller specimen than that required in conventional material tests. There are several methods, such as small-specimen creep test, the continuous indentation test, and small punch(SP) test. Among them, the small punch(SP) test method has been applied to many evaluation fields, such as a ductile-brittle transition temperature, stress corrosion cracking, hydrogen embrittlement, and fracture properties of advanced materials like FGM or MMC. In this study, the small punch(SP) test is performed to evaluate the mechanical properties at high/low temperature from $-196^{\circ}C$ to $650^{\circ}C$ and the material degradation for virgin and aged materials of 9Cr1MoVNb steel which has been recently developed. The ${\Delta}P/{\Delta}{\delta}$ parameter defined a slope in plastic membrane stretching region of SP load-displacement curve decreases according to the increase of specimen temperature, and that of aged materials is higher than the virgin material in all test temperatures. And the material degradation degrees of aged materials with $630^{\circ}C$ -500hrs and $630^{\circ}C$ -1000hrs are $36^{\circ}C$ and $38^{\circ}C$ respectively. These behaviors are good consistent with the results of hardness($H_v$) and maximum displacement(${\delta}_{max}$).

• Nuclear Engineering and Technology
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• 제38권5호
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• pp.405-410
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• 2006

Microstructural features and their related mechanical property changes in the 309L cladding and the heat affected zone (HAZ) of SA508 cl.3 steel were investigated through the use of TEM, tensile and small punch (SP) tests. The specimens were irradiated at 563 K up to the neutron fluences of $5.79{\times}10^{19}n/cm^2$ (>1MeV). The microstructure of the clad was mainly composed of a fcc ${\gamma}-phase$, a low percentage of bcc ${\delta}-ferrite$, and a brittle ${\sigma}-phase$. Along the weld fusion line there formed a heavy carbide precipitation with a width of $20{\sim}40{\mu}m$, showing preferential cracking during plastic deformation. The yield stress and ductile-to-brittle transition temperature (DBTT) of the irradiated clads increased. The origin of the hardening and the shift of the DBTT are discussed in terms of the irradiation-produced defect clusters of a fine size and brittle ${\sigma}-phase$.