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Featured researches published by Hyun-Gil Kim.


Journal of Nuclear Science and Technology | 2006

Out-of-pile and In-pile Perfomance of Advanded Zirconium Alloys (HANA) for High Burn-up Fuel

Yong Hwan Jeong; Sang-Yun Park; Myung Ho Lee; Byung-Kwon Choi; Jong-Hyuk Baek; Jeong-Yong Park; Jun-Hwan Kim; Hyun-Gil Kim

The performance of the advanced Zr alloys (HANA) for a high burn-up fuel has been evaluated in the out-of-pile and in-pile conditions. The corrosion resistance of the HANA claddings was superior to Zicaloy-4 in a PWR-simulating loop condition. The improved corrosion resistance of the HANA claddings was attributed to the fine distribution of the precipitate. HANA claddings showed a higher creep resistance as compared to Zircaloy-4 from the thermal creep test. The deformation behavior of HANA in a LOCA condition was similar to Zircaloy-4. Threshold ECR value of HANA was higher than the conventional value of 17% in Zircaloy-4, which is mainly due to the fact that the Nb decreases the oxidation rate as well as the hydrogen pickup. Fretting wear test revealed that HANA claddings have a similar wear resistance to Zircaloy-4. From the irradiation test up to burn-up of about 12 GWd/MtU, HANA claddings showed a better corrosion resistance as well as a better creep resistance than Zircaloy-4. The in-pile corrosion resistance of the HANA claddings was improved by 40–50% as compared to Zircaloy-4 on the basis of the oxide thickness measurements.


Journal of Nuclear Materials | 1999

Corrosion characteristics and oxide microstructures of Zircaloy-4 in aqueous alkali hydroxide solutions

Young-Hwan Jeong; Jong-Hyuk Baek; Sun-Doo Kim; Hyun-Gil Kim; H. Ruhmann

Abstract The corrosion characteristics of Zircaloy-4 have been investigated in various aqueous solutions of LiOH, NaOH, KOH, RbOH and CsOH with equimolar M + and OH − at 350°C. The characterization of the oxides was performed using transmission electron microscope (TEM) and scanning electron microscope (SEM) on the samples which were prepared to have an equal oxide thickness in pre-transition and post-transition regimes. At a low concentration (4.3 mmol) of aqueous alkali hydroxide solutions, the corrosion rates decrease gradually as the ionic radius of cation increases. At a high concentration (32.5 mmol), the corrosion rate increases significantly in LiOH solution and slightly in NaOH solution, but in the other hydroxide solutions such as KOH, RbOH and CsOH, the corrosion rate is not accelerated. Even if the specimens have an equal oxide thickness in LiOH, NaOH and KOH solutions, the oxide microstructure formed in the LiOH solution is quite different from those formed in the NaOH or the KOH solutions. In the LiOH solution, the oxides grown in the pre-transition regime as well as in the post-transition regime have an equiaxed structure including many pores and open grain boundaries. The oxides grown in the NaOH solution have a protective columnar structure in the pre-transition regime but an equiaxed structure in the post-transition regime. On the other hand, in the KOH solution, the columnar structure is maintained from its pre-transition regime to the post-transition regime. On the basis of the above results, it can be suggested that the cation incorporation into zirconium oxide would control the oxide microstructure, the oxide growth mechanism at the metal–oxide interface and the corrosion rate in alkali hydroxide solutions.


Nuclear Engineering and Technology | 2014

MICROSTRUCTURE AND MECHANICAL STRENGTH OF SURFACE ODS TREATED ZIRCALOY-4 SHEET USING LASER BEAM SCANNING

Hyun-Gil Kim; Il-Hyun Kim; Yang-Il Jung; Dong-Jun Park; Jeong-Yong Park; Yang-Hyun Koo

The surface modification of engineering materials by laser beam scanning (LBS) allows the improvement of properties in terms of reduced wear, increased corrosion resistance, and better strength. In this study, the laser beam scan method was applied to produce an oxide dispersion strengthened (ODS) structure on a zirconium metal surface. A recrystallized Zircaloy-4 alloy sheet with a thickness of 2 ㎜, and Y₂O₃ particles of 10 ㎛ were selected for ODS treatment using LBS. Through the LBS method, the Y₂O₃ particles were dispersed in the Zircaloy-4 sheet surface at a thickness of 0.4 ㎜, which was about 20% when compared to the initial sheet thickness. The mean size of the dispersive particles was 20 ㎚, and the yield strength of the ODS treated plate at 500oC was increased more than 65 % when compared to the initial state. This strength increase was caused by dispersive Y₂O₃ particles in the matrix and the martensite transformation of Zircaloy-4 matrix by the LBS.


Archive | 2015

Application of Coating Technology on Zirconium-Based Alloy to Decrease High-Temperature Oxidation

Hyun-Gil Kim; Il-Hyun Kim; Jeong-Yong Park; Yang-Hyun Koo

Since the Fukushima accident, it has been recognized that a hydrogen-related explosion is one of the major concerns regarding reactor safety during the hightemperature oxidation of zirconium alloys. To decrease the high-temperature oxidation rate of zirconium-based alloy, a coating technology for the zirconium alloy surface was considered. The selection of coating materials was based on the neutron cross-section, thermal conductivity, thermal expansion, melting point, phase transformation behavior, and high-temperature oxidation rate. After consideration of these factors, silicon was selected as a coating material for the first surface coating of zirconium-based alloy. A plasma spray and laser beam scanning were selected for the coating method, as both can be applied to a long tube shape without high-vacuum and high-temperature environments during the coating process. After Si-coated samples on Zircaloy-4 sheet had been prepared via plasma spray and combined plasma spray–laser beam scanning treatments,


Journal of Nuclear Materials | 2005

Phase boundary of the Zr-rich region in commercial grade Zr–Nb alloys

Hyun-Gil Kim; Jeong-Yong Park; Yong-Hwan Jeong


Journal of Nuclear Materials | 2005

Ex-reactor corrosion and oxide characteristics of Zr–Nb–Fe alloys with the Nb/Fe ratio

Hyun-Gil Kim; Jeong-Yong Park; Yong-Hwan Jeong


Journal of Nuclear Materials | 2015

Adhesion property and high-temperature oxidation behavior of Cr-coated Zircaloy-4 cladding tube prepared by 3D laser coating

Hyun-Gil Kim; Il-Hyun Kim; Yang-Il Jung; Dong-Jun Park; Jeong-Yong Park; Yang-Hyun Koo


Journal of Nuclear Materials | 2004

Crystal structure and grain size of Zr oxide characterized by synchrotron radiation microdiffraction

Jeong-Yong Park; Hyun-Gil Kim; Yong Hwan Jeong; Youn-Ho Jung


Surface & Coatings Technology | 2015

High temperature steam-oxidation behavior of arc ion plated Cr coatings for accident tolerant fuel claddings

Jung-Hwan Park; Hyun-Gil Kim; Jeong-Yong Park; Yang-Il Jung; Dong-Joon Park; Yang-Hyun Koo


Journal of Nuclear Materials | 2008

Microstructure and corrosion characteristics of Zr–1.5Nb–0.4Sn–0.2Fe–0.1Cr alloy with a β-annealing

Hyun-Gil Kim; Jong-Hyuk Baek; Sun-Doo Kim; Young-Hwan Jeong

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