• 한국자기학회지
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• 제7권4호
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• pp.205-211
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• 1997

E-Beam Evaporator로 제조된 CoCrTa/CrNi 자성박막에서 하지층인 Cr에 대한 소량첨가원소인 Ni이 자성박막의 자기적 성질에 어떤 영향을 미치는가를 조사하였다. 상온에서 제조된 시편에서 소량의 첨가원소 Ni의 영향은 보자력의 증가를 가져왔음을 알 수 있었다. 이러한 보자력 증가의 원인을 XRD와 AFM으로 그 결정배향성과 미세구조를 통하여 살펴보았다. Cr 하지층에 Ni의 첨가시 결정립의 크기가 증가함을 알 수 있었다. 280 .deg. C 기판온도에서는 CrNi 하지층을 갖는 박막이 오히려 낮은 보자력 값을 나타내었고 이것은 결정립 크기의 증가때문으로 생각된다. 높은 기판온도에서는 결정배향성보다 Cr의 편석이 보자력에 대한 주요한 기구인 것으로 생각된다.

• 대한금속재료학회지
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• 제48권2호
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• pp.122-132
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• 2010

Higher strength and fracture toughness of reactor pressure vessel steels can be obtained by changing the material specification from that of Mn-Mo-Ni low alloy steel (SA508 Gr.3) to Ni-Mo-Cr low alloy steel (SA508 Gr.4N). However, the operation temperature of the reactor pressure vessel is more than $300^{\circ}C$ and the reactor operates for over 40 years. Therefore, we need to have phase stability in the high temperature range in order to apply the SA508 Gr.4N low alloy steel for a reactor pressure vessel. It is very important to evaluate the temper embrittlement phenomena of SA508 Gr.4N for an RPV application. In this study, we have performed a Charpy impact test and tensile test of SA508 Gr.4N low alloy steel with changing impurity element contents such as Mn and P. And also, the mechanical properties of these low alloy steels after longterm heat treatment ($450^{\circ}C$, 2000hr) are evaluated. Further, evaluation of the temper embrittlement by fracture analysis was carried out. Temper embrittlement occurs in KL4-Ref and KL4-P, which show a decrease of the elongation and a shifting of the transition curve toward high temperature. The reason for the temper embrittlement is the grain boundary segregation of the impurity element P and the alloying element Ni. However, KL4-Ref shows temper embrittlement phenomena despite the same contents of P and Ni compared with SC-KL4. This result may be caused by the Mn contents. In addition, the behavior of embrittlement is not largely affected by the formation of $M_3P$ phosphide or the coarsening of Cr carbides.

• Journal of Welding and Joining
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• 제13권2호
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• pp.122-131
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• 1995

The effects of cooling rate on the microstructures, precipitation of Cu-cluster, .epsilon.-Cu and impact toughness of high strength low alloy(HSLA) steel were studied using hardness tester, impact tester, DSC(differential scanning calorimetry), AES(auger electron spectroscopy) and TEM(transmission electron microscopy). Not only the Cu-precipitates but also the segregation of Cu, As, Sb, P, S, N, Sn along grain boundary were not observed at the specimens heat treated from 800.deg. C to 300.deg. C with the cooling time of 12-125 sec. The Cu-cluster, .epsilon.-Cu are formed by introducing ageing after cooling and the effect of precipitates on hardening increase after cooling was the same in all cooling rate. The peak hardness was obtained at an ageing of 500.deg. C in all cooling conditions. The impact energy become higher as the cooling time increases. This fact can be explained to be due to the tempering effect applied on the cooling stage since the present alloy has a relatively high Ms temperature and the local high concentration of the retained austenite.

• 한국공작기계학회:학술대회논문집
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• 한국공작기계학회 2001년도 추계학술대회(한국공작기계학회)
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• pp.319-323
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• 2001

In significant number of energy-related facilities for like thermal power plant or petro-chemical industry, CrMo steels are widely used energy conversion industries. However, these materials undergo precipitation of carbides or intermetallic compounds into grain boundary and change of internal microstructure such as coarsening of precipitation, decrease of solute elements and impurity segregation under more severe service conditions, which results in deterioration of inherent superior material characteristics. In this study, it was verified experimentally the feasibility of the aging degradation evaluation for degraded 2.25Cr-lMo steel specimens prepared by isothermal aging heat treatment at 63$0^{\circ}C$ by high frequency longitudinal ultrasonic and surface SH wave investigating the change of attenuation coefficient analyzed by spectral analysis. Attenuation coefficient had a tendency to increase as degradation proceeded.

• 비파괴검사학회지
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• 제19권6호
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• pp.411-419
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• 1999

에너지 변환설비와 관련된 기계구조물의 내열재료는 $350^{\circ}C{\sim}550^{\circ}C$의 온도범위에서 장시간 사용되는데 이때 조직의 결정입계에는 불순물 원소(P, Sn, Sb등)의 편석과 탄화물의 석출 등으로 인하여 재료의 취화 현상이 발생되고, 그로 인해 입계강도의 저하가 초래된다. 따라서 노후화된 고온설비의 안전성 및 효율적인 운전조건을 확보하고, 취성파괴 방지를 위해서는 취화손상의 정량적 평가는 매우 중요하다. 그러나 가동중인 고온설비에서 파괴시험을 위한 대량의 시험편채취가 거의 불가능한 경우가 대부분이므로 비파괴적인 시험방법이 요구된다. 본 연구에서는 인공시효열처리된 2.25Cr-1Mo강의 비파괴적인 취화손상도 평가를 위해 적정 부식환경하에서 전기화학적 분극시험 방법에 의한 최적의 평가인자를 조사하였다. 또한 전기화학 시험결과들은 준비파괴시험인 SP시험에 의한 취화도 평가결과와 비교되었다.

• 분석과학
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• 제5권2호
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• pp.203-211
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• 1992

Ni-36.5at.%Al 합금에서 결정립계에서의 scavenging 원소로 알려진 V를 첨가하여 이 합금의 파괴거동 및 마르텐사이트 미세조직에 미치는 V의 영향에 대해 조사하였다. 시편의 파단면은 주사전자현미경으로 관찰하였고 EDX spectrometer를 사용하여 파단면의 조성을 분석하였으며 투과전자현미경으로 마르텐사이트 내부조직의 변화에 대해 조사하였다. V의 첨가로 입계파괴에서 입내파괴로 파괴 모드의 변화를 나타내었으며 EDX spectrometer로 분석한 결과 입내에 비해 입계에 Al의 함량이 상대적으로 증가되는 양상을 보여 주었다. Ni-36.5at.%Al 합금의 경우 마르텐사이트 플레이트는 내부쌍정으로 이루어져 있으나 V의 첨가에 따라 twinned 마르텐사이트 조직은 사라지며 stacking fault와 고밀도의 전위를 가진 modulated 조직이 점차 지배적으로 형성되는 것이 관찰되었다. Stacking fault를 분석한 결과 Al과 V의 치환에 따른 extrinsic fault였으며 high-energy 상태인 이 stacking fault가 있는 부위에 유해 원소인 S가 편석됨으로써 결정립계에서의 파괴를 줄일 수 있었다.

• 한국결정성장학회지
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• 제10권1호
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• pp.17-22
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• 2000

수직보자력이 크고 CoCrPt에 비하여 noise 저감 효과가 큰 것으로 알려진 CoCrPtTa계 합금박막의 수직이방성을 더욱 개선하기 위해 Ti를 우선 증착하였다. 본 연구에서는 Ti 두께 변화에 따른 비교적 높은 수직보자력치를 보였던 $CoCr_{16.2}Pt_{10.8}Ta_4$Ti/glass 시편에서 자기적 특성과 자구형상의 변화를 살펴보았다. 또한 VSM(Vibrating Sample Magnetometer)을 이용하여 M-H loop를 측정하였으며 자구형상은 MFM(Magnetic Force Microscopy)로 관찰하였다. 육방정 Ti가 하지층으로서 우선증착되면 bare glass 직접 증착되는 경우보다 CoCrPtTa 자성층의 수직이방성에 현저한 향상을 가져왔으며 Ti의 두께가 두꺼울수록 c-축 배향성도 개선되었다. MFM 결과에 의하면 Ti두레가 20 nm에서 90 nm로 증가함에 따라 자구형상이 연속적인 stripe type에서 mass type으로 분절된 형태로 변하였다. 이는 Ti의 증착이 비자성 Cr 편석 거동에 영향을 미쳐 자화반전시 인접 columnar grain의 자화벡터들간의 상호교환작용을 억제하는 자기적 분리 효과에 기여했음을 의미한다. 아울러 이와 같은 거동은 Ti가 CoCr계 자성층의 수직이방성을 개선하는데 있어서 형상자기이방성적인 측면에서의 기여가 현저함을 의미하기도 한다.

• 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.

• Journal of Welding and Joining
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• 제18권2호
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• pp.86-94
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• 2000

This study was performed to investigate types and formation mechanism of cracks in two Al alloy welds, A5083 and A7N01 spot-welded by pulse Nd : YAG laser, using SEM, EPMA and Micro-XRD. In the weld zone, three types of crack were observed : center line crack({TEX}$C_{C}${/TEX}), diagonal crack({TEX}$C_{D}${/TEX}), and U shape crack({TEX}$C_{U}${/TEX}). Also, HAZ crack({TEX}$C_{H}${/TEX}) was observed in the HAZ region, furthermore, mixing crack({TEX}$C_{M}${/TEX}) consisting of diagonal crack and HAZ crack was observed. White film was formed at th hot crack region in the fractured surface after it was immersed to 10% NaOH water. In the case of A5083 alloy, white films in {TEX}$C_{C}${/TEX} crack and {TEX}$C_{D}${/TEX} crack region were composed of low melting phases, {TEX}$Fe_{2}SiAl_{8}${/TEX} and eutectic phases, $Mg_2$Al$_3$ and $Mg_2$Si. Such films observed $CuAl_2$, {TEX}$Mg_{32}(Al,Zn)_{3}${/TEX}, MgZn$_2$, $Al_2$CuMg and $Mg_2$Si were observed in the whitely etched films near {TEX}$C_{C}${/TEX} crack and {TEX}$C_{D}${/TEX} crack regions. The formation of liquid films was due to the segregation of Mg, Si, Fe in the case of A5083 alloy and Zn, Mg, Cu, Sim in the case of A7N01 alloy, respectively. The {TEX}$C_{C}${/TEX} and {TEX}$C_{D}${/TEX} cracks were regarded as a result of the occurrence of tensile strain during the welding process. The formation of {TEX}$C_{M}${/TEX} crack is likely to be due to the presence of liquid film at the grain boundary near the fusion line in the base metal as well as in the weld fusion zone during solidification. The {TEX}$C_{U}${/TEX} crack is considered a result of the collapsed keyhole through incomplete closure during rapid solidification.

• Corrosion Science and Technology
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• 제20권3호
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• pp.158-168
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• 2021

Austenitic 316 stainless steel was irradiated with protons accelerated by an energy of 2 MeV at 360 ℃, the various defects induced by this proton irradiation were characterized with microscopic equipment. In our observations irradiation defects such as dislocations and micro-voids were clearly revealed. The typical irradiation defects observed differed according to depth, indicating the evolution of irradiation defects follows the characteristics of radiation damage profiles that depend on depth. Surface oxidation tests were conducted under the simulated primary water conditions of a pressurized water reactor (PWR) to understand the role irradiation defects play in surface oxidation behavior and also to investigate the resultant irradiation assisted stress corrosion cracking (IASCC) susceptibility that occurs after exposure to PWR primary water. We found that Cr and Fe became depleted while Ni was enriched at the grain boundary beneath the surface oxidation layer both in the non-irradiated and proton-irradiated specimens. However, the degree of Cr/Fe depletion and Ni enrichment was much higher in the proton-irradiated sample than in the non-irradiated one owing to radiation-induced segregation and the irradiation defects. The microstructural and microchemical changes induced by proton irradiation all appear to significantly increase the susceptibility of austenitic 316 stainless steel to IASCC.