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김현길,최병권,정용환,Kim Hyun Gil,Choi Byung Kyun,Jeong Yong Hwan 한국재료학회 2004 한국재료학회지 Vol.14 No.7
The effect of Cu addition on the corrosion characteristics of Zr alloys that developed for nuclear fuel cladding in KAERI (Korea Atomic Energy Research Institute) was evaluated. The alloys having different element of Nb, Sn, Fe, Cr and Cu were manufactured and the corrosion tests of the alloys were performed in static autoclave at $360^{\circ}C$, distilled water condition. The alloys were also examined for their microstructures using the optical microscope and the TEM equipped with EDS and the oxide property was characterized by using X-ray diffraction. From the result of corrosion test more than 450 days, the corrosion rate of the Zr-based alloys was changed with alloying element such as Nb, Sn, Fe, Cr and especially affected by Cu addition. The corrosion resistance was increased with increasing the Cu content and the tetragonal $ZrO_2$ layer was more stabilized on the Cu-containing alloys.
핵연료 안내관용 지르코늄 합금의 강도 및 부식 성능에 미치는 제조공정 영향
김현길 ( Hyun Gil Kim ),김일현 ( Il Hyun Kim ),최병권 ( Byung Kwan Choi ),박상윤 ( Sang Yoon Park ),박정용 ( Jeong Yong Park ),정용환 ( Yong Hwan Jeong ) 대한금속·재료학회 2009 대한금속·재료학회지 Vol.47 No.12
The manufacturing process of zirconium alloys is an import factor to increase their strength and corrosion resistance. In order to find an improved manufacturing process of zirconium alloys in both Zr-1Nb-1Sn-0.1Fe (Alloy-A) and Zr-1.5Nb-0.4Sn-0.2Fe-0.1Cr (HANA-4) for fuel guide tubes, sheet samples were prepared by applying two- and three-step processes that were controlled by an annealing and reduction condition. The mechanical strength and corrosion resistance of both alloys were increased by applying the two-step process rather than the three-step process. From a matrix analysis using TEM, the property improvement is related to the decrease of the precipitate mean diameter with an application of the two-step process. In a comparison of the strength and corrosion properties between Alloy-A and HANA-4, the performance of HANA-4 was feasible for application to fuel guide tubes.
김현길 ( Hyun Gil Kim ),김일현 ( Il Hyun Kim ),박상윤 ( Sang Yoon Park ),박정용 ( Jeong Yong Park ),정용환 ( Yong Hwan Jeong ) 대한금속재료학회 ( 구 대한금속학회 ) 2010 대한금속·재료학회지 Vol.48 No.8
The degradation behavior of fuel cladding is a very import concern in nuclear power generation, because the operation of nuclear plants can be limited by fuel cladding degradation. In order to evaluate the hydride effect on failure of zirconium fuel claddings, a ring tensile test for the circumferential direction was carried out at room temperature for claddings having different hydride characteristics such as density and orientation; microstructural evaluation was also performed for those claddings. The circumferential failure of the claddings was promoted by increasing the hydride concentration in the matrix; however, the failure of the claddings was affected by the hydride orientation rather than by the hydride concentration in the matrix. From fracture surface observation, the cladding failure during the ring tensile test was matched with the hydride orientation.
논문 : 기계적 성질 ; 핵연료피복관용 지르코늄 합금의 크리프 거동에 미치는 합금원소의 영향
김현길 ( Hyun Gil Kim ),최병권 ( Byoung Kwon Choi ),정용환 ( Yong Hwan Jeong ) 대한금속재료학회 ( 구 대한금속학회 ) 2007 대한금속·재료학회지 Vol.45 No.9
In order to evaluate the thermal creep properties of the zirconium alloy for nuclear application as fuel cladding, the creep test for the four types of the zirconium fuel cladding tubes which had different compositions was carried out by the internal pressurization method in the temperature of 400℃ and the hoop stress range from 100 to 150 MPa. Creep tests were performed up to 200 days, which showed the steady-state secondary creep rate. From the results of the creep test for the four types of the zirconium cladding tubes, the creep strain of those fuel claddings was gradually increased with increasing applied stress regardless of alloy composition. The alloying elements such as Sn, Nb were more effective in the creep resistance than other elements such as Fe, Cr, Mn and Cu, since the solubility of Sn and Nb in a-zirconium was higher than other elements. Therefore, to increase the creep property of the zirconium alloy it is necessary for the control of the alloying elements which have larger soluble limit in a-zirconium.
고온 코팅용 Cr-Al합금의 미세조직 및 특성에 미치는 Si 첨가의 영향
김정민,김일현,김현길,Kim, Jeong-Min,Kim, Il-Hyun,Kim, Hyun-Gil 한국재료학회 2019 한국재료학회지 Vol.29 No.1
Cr-Al alloys are attracting attention as oxidation resistant coating materials for high temperature metallic materials due to their excellent high temperature stability. However, the mechanical properties and oxidation resistance of Cr-Al alloys can be further enhanced, and such attempts are made in this study. To improve the properties of Cr-Al alloys, Si is added up to 5 wt%. Casting specimens with different amounts of Si content are prepared by a vacuum arc remelting method and isothermally heated under steam conditions at $1,100^{\circ}C$ for 1 hour. The as-cast microstructure of low Si alloys is mainly composed of only a Cr phase, while $Al_8Cr_5$ and $Cr_3Si$ phases are also observed in the 5 % Si alloy. In the high Si alloy, only Cr and $Cr_3Si$ phases remain after the isothermal heating at $1,100^{\circ}C$. It is found that Si additions slightly decrease the oxidation resistance of the Cr-Al alloy. However, the microhardness of the Cr-Al alloy is observed to increase with an increasing Si content.
김윤호,목용균,김현길,이종현,Kim, Yoon-Ho,Mok, Yong-Kyoon,Kim, Hyun-Gil,Lee, Jong-Hyeon 한국재료학회 2015 한국재료학회지 Vol.25 No.8
The effects of Nb and Cr addition on the microstructure, corrosion and oxide characteristics of Zr based alloys were investigated. The corrosion tests were performed in a pressurized water reactor simulated-loop system at $360^{\circ}C$. The microstructures were examined using OM and TEM, and the oxide properties were characterized by low-angle X-ray diffraction and TEM. The corrosion test results up to 360 days revealed that the corrosion rates were considerably affected by Cr content but not Nb content. The corrosion resistance of the Zr-xNb-0.1Sn-yCr quaternary alloys was improved by an increasing Nb/Cr ratio. The crystal structure of the precipitates was affected by a variation of the Nb/Cr ratio. The Zr-Nb beta-enriched precipitates were mainly formed in the high Nb/Cr ratio alloy while $Zr(NbCr)_2$ precipitates were frequently observed in the low Nb/Cr ratio alloy. The studies of oxide characteristics revealed that the corrosion resistance was related to the crystal structure of the precipitate.