• Corrosion Science and Technology
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• v.18 no.1
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• pp.33-38
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• 2019

Alloy 600/182 with excellent mechanical/chemical properties have been utilized for nuclear power plants. Although both alloys are known to have superior corrosion resistance, stress corrosion cracking failure has been an issue in primary water environment of nuclear power plants. Therefore, primary water stress corrosion crack (PWSCC) growth rate tests were conducted to investigate crack growth properties of Alloy 600/182. To investigate PWSCC growth rate, test facilities including water chemistry loop, autoclave, and loading system were constructed. In PWSCC crack growth rate tests, half compact-tension specimens were manufactured. These specimens were then placed inside of the autoclave connected to the loop to provide primary water environment. Tested conditions were set at temperature of $360^{\circ}C$ and pressure of 20MPa. Real time crack growth rates of specimens inside the autoclave were measured by Direct Current potential drop (DCPD) method. To confirm inter-granular (IG) crack as a characteristic of PWSCC, fracture surfaces of tested specimens were observed by SEM. Finally, crack growth rate was derived in a specific stress intensity factor (K) range and similarity with overseas database was identified.

• Journal of Magnetics
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• v.16 no.3
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• pp.229-233
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• 2011

Phase evolution during the hydrogen-assisted disproportionation of $Nd_{12.5}Fe_{80.6}B_{6.4}Ga_{0.3}Nb_{0.2}$ alloy was investigated mainly by using a magnetic balance-type thermomagnetic analyser (TMA). In order to avoid any undesirable phase change in the course of heating for TMA, a swift TMA technique with very high heating rate (around 2 min to reach $800^{\circ}C$ from room temperature) was adopted. The hydrided $Nd_{12.5}Fe_{80.6}B_{6.4}Ga_{0.3}Nb_{0.2}$ alloy started to be disproportionated in hydrogen from around $600^{\circ}C$, and the alloy after the early disproportionation (from 600 to $660^{\circ}C$) has been partially disproportionated. The partially disproportionated alloy consisted of a mixture of $NdH_x$, $Fe_3B$, ${\alpha}$-Fe, and the remaining undisproportionated $Nd_2Fe_{14}BH_x$-phase. During the subsequent heating to $800^{\circ}C$ in hydrogen, two additional phases of $Fe_{23}B_6$ and $Fe_2B$ were formed, and the material consisted of a mixture of $NdH_x$, $Fe_{23}B_6$, $Fe_3B$, $Fe_2B$, and ${\alpha}$-Fe phases. During the subsequent isothermal holding at $800^{\circ}C$ for 1 hour, the phase constitution was further changed, and one additional unknown magnetic phase was formed. Eventually, the fully disproportionated $Nd_{12.5}Fe_{80.6}B_{6.4}Ga_{0.3}Nb_{0.2}$ alloy consisted of $NdH_x$, $Fe_{23}B_6$, $Fe_3B$, $Fe_2B$, ${\alpha}$-Fe, and one additional unknown magnetic phase.

• Journal of the Korean Society of Manufacturing Process Engineers
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• v.10 no.6
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• pp.1-8
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• 2011

Recently, super heat-resistant alloy Inconel 600 come into spotlight as the material of airplane parts but this material causes lots of problems that is, reduction of machinability and attritious wear and breakage of cutting tool during turning processing due to high temperature strength and cohesion between tool material and Inconel 600. Therefore, in this study, it was purposed to determine tool material kind and to select of proper cutting range when turning process was carried out for Inconel 600. In order to these Purpose, coated carbide tool and ceramic tool was used in this experiment and the machinability of Inconel 600 was investigated from perspective of the cutting force, chipping and wear of tool and deposition phenomenon of chip.

• Journal of Welding and Joining
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• v.33 no.1
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• pp.14-23
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• 2015

Recent developing tendency of nuclear power plant are studied by searching of NDSL, KIPRIS, Science Direct and so on. Welding materials such as low alloyed steels, stainless steels, nickel-based alloys, zirconium alloy and welding methods such as narrow gap welding, laser beam welding, friction stir welding, overlay welding are investigated.

• Journal of the Korean institute of surface engineering
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• v.21 no.1
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• pp.10-18
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• 1988

The variation of Composition and the microstructure of Zn-Ni alloy electrodespposits were investigated to the electrolysis conditions chloride bath. The codeposition mechanism is of the equilibrium type in the electrolysis condition of the high temperature(6$0^{\circ}C$)and high flow rate (1.2-3.0m/sec). The(411, 330) perferred orienation was mainly developed in the Zn-Ni electrodeposir with ${\gamma}$-phase structure, while the(422.600) orientation was closely related to the commposition and the structure of the alloy electrodeposit.

• Korean Journal of Metals and Materials
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• v.47 no.8
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• pp.482-487
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• 2009

In order to investigate the effects of intermediate heat treatment between cold rolling passes on the hardness and corrosion properties of a Zr alloy incorporating Nb (Zr-1.49Nb-0.38Sn-0.20Fe-0.11Cr) strip, three different intermediate heat treatment processes ($580^{\circ}C{\times}4hrs$, $600^{\circ}C{\times}2hrs$ and $620^{\circ}{\times}1hrs$) were designed based on a recrystallization map and an accumulated annealing parameter. Test samples from the different processes were investigated by a hardness test, corrosion test, and microstructure analysis and appropriate heat-treatment conditions were thereupon proposed. The sample subjected to an intermediate heat treatment of $580^{\circ}C{\times}4hrs$ was harder than that undergoing $600^{\circ}C{\times}2hrs$ and $620^{\circ}C{\times}1hr$ while the corrosion resistance of the sample that received an intermediate heat treatment of $580^{\circ}C{\times}4hrs$ was superior to that of the other specimens. Considering the trade-off of hardness and corrosion resistance, an intermediate heat treatment process of $600^{\circ}C{\times}2hrs$ is proposed to improve the manufacturing process of the alloy strip.

• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.284-284
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• 2001

• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.547.2-547
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• 2001

• Proceedings of the Korean Nuclear Society Conference
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• 2003.05a
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• pp.240-240
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• 2003

• Proceedings of the Korean Nuclear Society Conference
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• 2005.05a
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• pp.529-530
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• 2005