• 한국진공학회:학술대회논문집
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• 한국진공학회 1994년도 제6회 학술발표회 논문개요집
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• pp.35-35
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• 1994

The surface segragation of NiZr, CuZr alloy has been studied wi th X-ray Imotoelectron spectroscopy(XPS), Auger electron spectroscopy(AES) and low energy ion scattering(LEIS). The composition of outmost atomic layer has been determinded by the use of LEIS at several incident energies using Ar+ ion. In the LEIS analysis, the effect of charge exchange has been estimated by a novel measurment of the charge exchange parameters while simul taneous determining the relative concentrations of Ni and Zr and the complementary information obtained will be described. The composition of the clean annealed surface, measured with AES only, will be contrasted wi th the surface concentration of the preferentially sputtered surface. The experimental results has been clearly demonstrated that when the NiZr ruld CuZr alloys are exposed to continuous Ar+ ion bombardment the outermost atomic layer is Zr rich due to preferential sputtering of Ni atoms. where Ni is preferentially sputtered, but the difference in sputtering yields is not sufficient to explain the observed composition. Therefore, it is necessary to consider other processes such as Radiation Induced Segregation(RIS). The surface composition of the heated sample surface predicts that Zr should surface segregate which futher supports the view that part of the Zr enrichment is due to RIS.to RIS.

• 열처리공학회지
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• 제7권2호
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• pp.96-102
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• 1994

The present work was aimed to examine the changes of the shape and particle size distribution(PSD) of ${\delta}^{\prime}$ particles on ageing in Al-Li-(Cu, Zr) alloys which had low density, high specific strength and stiffness, Increasing ageing time and temperature resulted in particles whose aspect ratio tended toward 1. The aspect ratio of ${\delta}^{\prime}$ particles was not dependent upon the ageing temperature and time in Al-Li-Cu alloy but was dependent upon them in Al-Li-Zr alloy. The PSD of ${\delta}^{\prime}$ particles in Al-Li-Zr alloy skewed to the right hand compared with that in Al-Li-Cu alloy, because $Al_3Zr$ phase in Al-Li-Zr alloy formed before ageing promoted the precipitation and growth of ${\delta}^{\prime}$ phase. Therefore, the PSD of the ${\delta}^{\prime}$ particles was found to be affected by the presence of $Al_3Zr$ particles. The growth rate of ${\delta}^{\prime}$ phase was not affected by the existence of the third transition phase $T_1$ formed by the addition of Cu in Al-Li alloy but was affected by the existence of $Al_3Zr$ formed by the addition of Zr in Al-Li alloy.

• 한국주조공학회지
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• 제34권2호
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• pp.49-53
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• 2014

In commercial Zr-Nb-Cu-Ni-Al amorphous alloys, expensive element, Zr, was substituted to Sn which was cheaper one, and then, glass forming ability, compressive strength and hardness of them were estimated. Even though the Sn was added up to 1.5%, resulting phase was not changed to the crystalline form. It was confirmed by X-ray diffraction and thermal analyses. In the X-ray profiles, there were no peaks for crystalline phases and typical halo pattern for amorphous phase was appeared at the diffraction angle of $35^{\circ}{\sim}45^{\circ}$. Thermal analyses also showed that the Sn modified alloys were corresponded to the amorphous standards where ${\delta}T$(= Tx - Tg) and Trg(= Tg/Tm) affecting to the amorphous forming ability were more than 50K and 0.60 respectively. Compressive strengths were 1.77 GPa, 1.63 GPa, 1.65 GPa and 1.77 GPa for 0%Sn, 0.5%Sn, 1.0%Sn and 1.5%Sn respectively. Hardnesses of the Sn modified alloys were decreased from 752 Hv to 702 Hv in 1.0%Sn and recovered to 746 Hv in 1.5%Sn.

• Corrosion Science and Technology
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• 제2권6호
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• pp.253-259
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• 2003

Zirconium based alloys have been extensively used as a cladding material for fuel rods in nuclear reactors, due to their low thermal neutron absorption cross-section, excellent corrosion resistance and good mechanical properties at high temperatures. However, a cladding material for fuel rods in nuclear reactors was contact water during long time at high-temperature, so it is necessary to improve the wear and corrosion resistance of the fuel cladding, At ambient environment, there are few data or paper on the characteristic of corrosion in chloride solution and acidic solution. The specimens used in this work are pure Zr and Zircaloy-4. Zircaloy-4 is a specific zirconium-based alloy containing, on a weight percent basis, 1.4% Sn, 0.2% Fe, 0.1% Cr. Pitting corrosion resistance of two alloys by ASTM G48 is higher than that of electrochemical method. Passive film formed on Zircaloy-4 is mainly composed of $ZrO_2$, metallic Sn, and iron species regardless of formation environments. Also, passive film formed on Zr alloys shows n-type semiconductic property on the base of Mott-Schottky plot.

• 열처리공학회지
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• 제18권1호
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• pp.12-17
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• 2005

Effects of Zn and Zr additions on the microstructure and mechanical properties of Al-5%Mg-1%Mn alloys were investigated. As Zn content increased in the Al-Mg-Mn-Zn alloys, the tensile strength and ductility of as-cast alloys rather decreased while the tensile strength of the heat-treated alloys significantly increased mainly due to the precipitation of fine $MgZn_2$ phases. Small amount of Zr was added to the 3%Zn alloy to further enhance the mechanical properties, and it appeared to increase the strength and ductility, especially in as-cast state.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2003년도 가을 학술논문집
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• pp.395-400
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• 2003

사용후핵연료 금속전환체의 장기저장 안정성 확보를 위해 금속전환체의 주성분인 금속우라늄과 산화 안정화 후보물질인 Nb, Ti, Ni, Zr, Hf 등을 첨가한 모의금속전환체 합금을 제작하여 $200^{\circ}C~300^{\circ}C$ 온도구간에서 순수 산소분위기로 산화시험을 수행하였다. U-Nb, U-Zr, U-Ti 합금은 순수 금속우라늄보다 무게증가 측면에서의 산화저항성이 높았으나, U-Hf, U-Ni 합금의 경우에는 오히려 순수 금속우라늄보다 산화 저항성이 낮게 나타났다. 시편에 대한 미세성분 및 조직을 광학현미경, SEM, EPMA 등을 통해 분석하였다. 각 합금의 산화율 및 활성화에너지를 구한 결과 U-Nb 합금의 활성화에너지가 높고 산화 저항성이 가장 양호한 것으로 나타나 산화 저항성 후보물질로 선정하였다.

• Journal of Magnetics
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• 제4권4호
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• pp.131-135
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• 1999

The HDDR characteristics of the Nd-Fe-B-type isotropic and anisotropic HDDR alloys were investigated using three types of alloys: alloy A $(Nd_{12.6}Fe_{81.4}B_6), alloy B (Nd_{12.6}Fe_{81.3}B_6Zr_{0.1}), and alloy C (Nd_{12.6}Fe_{68.8}Co_{11.5}B_6Ga_{1.0}Zr_{0.1}$). The alloy A is featured with the isotropic HDDR character, while alloy B and C are featured with the anisotropic HDDR character. Hydrogenation and disproportionation characteristics of the alloys were examined using DTA under hydrogen gas. Recombination characteristics of the alloys were examined by observing the coercivity variation as a function of recombination time. The present study revealed that the alloy C exhibits slightly higher hydrogenation and disproportionation temperatures compared to the alloy A and B. Recombination of the anisotropic alloy B and C takes place more rapidly with respect to the isotropic alloy A. The intrinsic coercivities of the recombined materials rapidly increased with increasing the recombination time and then showed a peak, after which the coercivities decreased gradually. The degraded coercivity was, however, recovered significantly on prolonged recombination treatment. Compared with the isotropic HDDR alloy A the anisotropic HDDR alloy B and C are notable for their greater recovery of coercivity. The significant recovery of coercivity was accounted for the in terms of the development of well-defined smooth grain boundary between the recombined grains on prolonged recombination.

• 한국재료학회지
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• 제12권4호
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• pp.259-263
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• 2002

Three different ribbons of amorphous $Til_{1-x}Be_x$ alloys such as $Ti_{0.59}Be_{0.41},\;Ti_{0.61}Be_{0.39}\;and\;Ti_{0.63}Be_{0.37}$ were made by melt-spinning method to be used as brazing filler metals for joining Zircaloy-4 nuclear fuel cladding tubes, and their crystallization behavior as well as microstructure of the brazed zone were examined. The crystallization behavior was investigated in teams of thermal stability, crystallization temperature and activation energy. The crystallization of the $Ti_{1-x}Be_x$ alloys proceeded in two steps by the formation of ${\alpha}$-Ti at a lower temperature and of TiBe at a higher temperature. The crystallization temperature and activation energy of $Ti_{1-x}Be_x$ alloys were higher and larger than those of $Zr_{1-x}Be_x$ alloys and PVD Be. Those resulted thinner joining layer with $Ti_{1-x}Be_x$ alloys, which kept sound thickness of Zircaloy-4 nuclear fuel cladding tubes after brazing. But in the brazed zones made by $Ti_{1-x}Be_x$ filler metals, a little solid-solution layers composed of Zr and Ti were formed toward the Zr cladding tube and Zr was detected in the brazed zones. Microstructure of brazed zone was changed from globular to dentrite with decreasing Be content in the $Ti_{1-x}Be_x$ filler metal.

• 한국재료학회지
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• 제12권5호
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• pp.369-374
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• 2002

To investigate the corrosion behavior of Zr-1.0Nb-xSn (x=1.0, 1.5, 2.0 and 2.5wt. %)alloy system, the corrosion tests of Zr-1.0Nb-xSn alloys were carried out in steam at $400^{\circ}C$ for 125 days and in 70ppm LiOH solution at $360^{\circ}C$ for 180 days. The matrix microstructures of the test specimens were analyzed using TEM and the oxide structures on the test specimens were analyzed using XRD. It was found from the analyses that the more Sn content the alloy had, the faster it was corroded and with the increase of Sn content in the alloy the fraction of $t-ZrO_2$ to $m-ZrO_2$ was decreased. It was also found that the alloys having more Sn showed more dislocation density than those having less.

• 한국재료학회지
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• 제8권12호
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• pp.1099-1109
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• 1998

Zr합금에서 V, Sb의 함랗 변화가 Zr 합금의 부식 특성에 미치는 영향을 조사하기 위해 V, Sb함량을 각각 0.1, 0.2, 0.4wt.% 변화시킨 6종의 합금을 제조하고$ 360^{\circ}C$ 물 분위기에서 100일 동안 부식실험을 수행하였다. V이 0.2, 0.4wt% 첨가시편에서는 부식 속도의 천이 현상이 관찰되지 않았으나 0.1wt.% V 첨가 시편의 경우 10일 이후부터 무게증가량이 급격히 증가하는 부식 속도 가속 현상이 발생하였다. V 첨가량이 증가할수록 내식성이 증가하였으며 0.4wt.%V 첨가 합금이 가장 우수한 내식성을 보였다. Sb가 첨가된 삼원계 합금에서는 0.1, 0.4wt.%Sb 첨가 시편의 경우 초기부터 급격히 부식이 가속되는 현상이 발생하였으며 Sb 첨가량이 증가할수록 무게증가량이 감소하다가 다시 증가하여 0.2wt.% Sb 첨가에서 최소 무게증가량을 보였다. V, Sb함량이 증가할수록 석출물의 크기와 석출물의 부피 분율이 증가하는 경향을 보였으며 석출물의 크기가 0.11-0.13$\mu\textrm{m}$의 석출물 크기를 가질 때 가장 우수한 내식성을 보였다. 부식특성과 석출물 크기와의 관계로부터 적절한 크기의 석출물은 음극반응에서 전자의 전도를 제어하고 안정한 산화막 미세구조를 유지하는데 중요한 역할을 한다고 사료된다.