• Proceedings of the Korean Institute of Surface Engineering Conference
• /
• 2012.11a
• /
• pp.121-122
• /
• 2012

합금도금강판의 일시 방청과 기능성 부여 후처리는 크로메이트, 인산염처리 등과 같은 방법을 시행하는 것이 일반적이다. 최근에는 아연합금도금 강판의 사용 및 보관 환경이 가혹해짐에 따라 보다 우수한 일시 방청성과 내식성이 요구되고 있다. 본 연구는 솔젤법을 이용하여 zirconium n-propoxide와 3-glycidoxypropyltrimethoxysilane(GPTS)으로부터 중합된 코팅막과 이에 zirconia nanoparticle입자를 첨가한 코팅막의 공극율(prosity)과 방식효율(protective efficiency)을 분극데이터를 이용하여 비교 평가하였으며, 염수분무시험을 통해 내식성 평가를 진행하였다.

• Nuclear Engineering and Technology
• /
• v.52 no.8
• /
• pp.1724-1731
• /
• 2020

Low cycle fatigue tests on the hydrogenated welding seam of Zr-Sn-Nb alloy at room temperature and 360 ℃ had been carried out by using the funnel-shaped flat specimens. The relationships between nominal stress & strain directly measured across the funnel and local stress & strain at the root of the funnel are given by considering cyclic plasticity correction. The results show that the fatigue resistance of welding seam at room temperature is only slightly better than that at 360 ℃. Probabilistic fatigue life curves are obtained by using a two-parameter power function.

• Nuclear Engineering and Technology
• /
• v.51 no.2
• /
• pp.518-525
• /
• 2019

The mechanical and corrosion behavior of the Russian zirconium fuel cladding alloy E110, predominantly used in VVERs, has been investigated for many decades. The recent commercialization of a new, optimized E110 alloy, produced on a sponge zirconium basis, gave the opportunity to compare the mechanical properties of the old and the new E110 fuel claddings. Axial and tangential tensile test experiments were performed with samples from both claddings in the MTA EK. Due to the anisotropy of the cladding tubes, the axial tensile strength was 10-15% higher than the tangential (measured by ring tensile tests). The tensile strength of the new E110G alloy was 11% higher than that of the E110 cladding at room temperature. Some samples underwent chemical treatment - slight oxidation in steam or hydrogenation - or heat treatment - in argon atmosphere at temperatures between 600 and $1000^{\circ}C$. The heat treatment during the oxidation had more significant effect on the tensile strength of the claddings than the oxidation itself, which lowered the tensile strength as the thickness of the metal decreased. The hydrogenation of the cladding samples slightly lowered the tensile strength and the samples but they remained ductile even at room temperature.

• Korean Journal of Metals and Materials
• /
• v.47 no.12
• /
• pp.852-859
• /
• 2009

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 twostep 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.

• Journal of the Korean Society for Heat Treatment
• /
• v.17 no.3
• /
• pp.151-164
• /
• 2004

The changes of microstructural and mechanical properties were evaluated for the high burn-up fuel claddings after the neutron irradiation of $1.8{\sim}3.1{\times}10^{20}n/cm^2$ (E>1.0 MEV) in HANARO research reactor. After the irradiation, the spot-type dislocations (a-type dislocations) were easily observed in most claddings, and the density of the dislocations was different depending on the grains and was higher at grain boundaries than within grains. As the final annealing temperature increased, the density of spot-type dislocations increased and the line-type dislocations (c-type dislocations) which was perpendicular to the <0002> direction, appeared sporadically in some claddings. However, the types of precipitates in the fuel claddings after the irradiation were not changed from that in unirradiated claddings. The mechanical properties including the hardness, strength and elongation after the irradiation were changed due to the formation of spot-type dislocations. That is, the increase in hardness and strength as well as the decrease in elongation after the irradiation was occurred simultaneously with increasing the final annealing temperature. Owing to the Nb contribution to the formation of spot-type dislocation during the irradiation, the increase in hardness and strength in higher Nb-contained Zr alloys after the irradiation was higher than that in lower Nb-contained Zr alloys.

• Transactions of the Korean Society of Mechanical Engineers A
• /
• v.35 no.3
• /
• pp.281-287
• /
• 2011

We consider the uncertainty in the elastic buckling formula for a thin tube. We take into account the measurement uncertainty of Young's modulus and Poisson's ratio and the tolerance of the tube thickness and diameter. Elastic buckling must be prohibited for a thin tube such as a nuclear fuel rod that must satisfy a self-stand criterion. Since the predicted critical buckling pressure overestimated that found in the experiment, the determination of the minimum safety factor is crucial. The uncertainty in each parameter (i.e., Young's modulus, Poisson's ratio, thickness, and diameter) is mutually independent, so the safety factor is evaluated as the sum of the inverse of each uncertainty. We found that the thickness variation greatly affects the uncertainty. The minimum safety factor of a thin tube of Zirconium alloy is evaluated as 1.547 for a thickness of 0.87 mm and 3.487 for a thickness of 0.254 mm.

• Korean Journal of Metals and Materials
• /
• v.46 no.8
• /
• pp.482-488
• /
• 2008

For a better understanding of the correlation between a corrosion and a microstructure, it is necessary to study a phase transformation with an annealing condition for Zr-Nb alloy. Zr-5wt.%Nb alloy with different phase characteristics was prepared with various annealing conditions. A microstructural study and corrosion test were performed to investigate the effect of a phase such as the phase type, fraction, and size on corrosion. The corrosion behavior of the Zr-5Nb alloy was very sensitive to the annealing condition, which affected the formation of the ${\beta}$-phases (${\beta}$-Nb or ${\beta}$. The corrosion rate of the Zr-5Nb alloy annealed at $500^{\circ}C$ with the formation of the ${\beta}$-Nb phase was lower than that of the Zr-5Nb alloy annealed from 600 to $800^{\circ}C$ with the formation of the ${\beta}$-Zr phase. The highest corrosion rate was observed for the ${\beta}$-quenched Zr-5Nb alloy. After a consideration of the corrosion rate and micro structure of the Zr-5Nb alloy, the corrosion resistance of that alloy was improved due to the formation of a small sized ${\beta}$-Nb phase which could be controlled by the annealing condition.

• Journal of the Korean Society of Propulsion Engineers
• /
• v.7 no.4
• /
• pp.73-79
• /
• 2003

The tensile strength test and the analysis for the section of brazing were performed in the cases of materials used for combustion chamber of regeneratively cooled liquid rocket engine. BNi-2 and BNi-7 based on nickel were used for brazing as filler metal. The properties of material and filler metal were analyzed by tensile strength test and metal microscope for 12 specimens. The tensile-strength of brazing for chrome-copper alloy and other kinds of alloy was higher than that of chrome-zirconium-copper alloy and other kinds of alloy The tensile strength in the case of BNi-2 as filler metal was higher than that of BNi-7 because the wetting property of BNi-2 was better than that of BNi-7.

• Journal of the Korea Academia-Industrial cooperation Society
• /
• v.21 no.7
• /
• pp.82-89
• /
• 2020

Among the explosives in ammunition, the delay elements, which are used as a retardant, could be influenced by the ambient temperature in the Republic of Korea, where the highest and lowest average annual temperature difference is clear. On the other hand, there has been no domestic research on this. This study examined the linear burning rates of the zirconium-nickel delay elements depending on the ambient temperature in South Korea. The ambient temperature data of South Korea were obtained from the meteorological administration, which was used to set the experimental conditions. The operational time for the K414 fuze was measured by changing the ambient temperature by 10 ℃ from -40 ℃ to 50 ℃. To convert the delay time into the burning rates, the height of the delay element in the K414 fuze body was used. The results indicated that the characteristics of the burning rates for the zirconium-nickel delay element could be estimated as linear, and both the burning rates and the delay time of the zirconium-nickel delay element were 2.73mm/ms and -4.18ms, respectively. This led to an approximately 80 ms delay time difference in the environment where the highest and lowest average annual temperature difference was above 20 ℃. Therefore, the delay time reflecting the ambient temperature should be considered when the test evaluation criteria of zirconium-nickel delay elements are established.

• Proceedings of the KWS Conference
• /
• 1995.04a
• /
• pp.65-67
• /
• 1995

The solidification crack susceptifility of aluminum alloy weld metal have been evaluated by means of the slef restraint and external restraint cracking test. It has been observed expermently as follows : (1) The manganese is beneficial to decrease the solidification cracking susceptibility. (2) Weld metal containing zirconium is less sensitive to the solidification cracking than the weld metal containing chromium does. (3) The self restraint test method shows the same tendency in results as the external restraint test does.