• 한국재료학회지
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• 제8권4호
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• pp.368-374
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• 1998

Zr합금의 부식거동을 평가하기 위하여 여러 가지 1족 알칼리 수산화물 용액 (LiOH, NaOH, KOH, RbOH, CsOH)에서 autoclave를 이용하여 300일까지 부식시험을 실시하였다. 산화막 특성은 TEM을 이용하여 천이전과 천이후에 동일 산화막두께를 갖도록 준비된 부식시편에 대해 수행되었다. 실험결과를 고려할 때 금속이온은 부식과정에서 매우 중요한 역할을 하는 것으로 사료된다. 즉 $Li^+$가 $Zr^{4+}$ 치환하여 산소농도는 증가하고 부식은 가속되는데 산화막 내부의 barrier layer에서 $Li^-$치환이 부식을 제어하는 것으로 판단된다.동일 두께의 산화막 일지라도 산화막의 구조는 모두 다르다. 32.5mmol LiOH에서 생성된 산화막온 천이전,후에 관계 없이 많은 기공이 함유된 등축정 구조를 갖는다. 반면에 NaOH에서 생성된 산화막은 천이전에는 주상정 구조를 갖지만 천이후에는 다공성의 등축정 구조로 바뀐다. KOH용액에서는 천이전에는 주상정과 비정질 산화막의 이중 구조를 갖지만 천이후에는 비정질 산화막은 사라직 전반적으로 주상정 구조가 형성된다. 부식거동과 산화막 관찰로부터 금속이온의 산화막내 치환이 부식속도와 산화막 미세구조를 지어한다는 것을 알 수 있었다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2001년도 춘계학술발표회요약집
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• pp.313.1-313
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• 2001

• 한국신재생에너지학회:학술대회논문집
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• 한국신재생에너지학회 2007년도 춘계학술대회
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• pp.49-52
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• 2007

We investigated hydrogen storage and production properties using redox system of iron oxide($Fe_{3}O_{4}$ + $4H_{2}$ ${\leftrightarrows}$ 3Fe + $4H_{2}O$) modified with rhodium, ceria and zirconia under atmospheric pressure. Reduction of iron oxide with hydrogen(hydrogen storage) and re-oxidation of reduced iron oxide with steam(hydrogen evolution) was carried out using a temperature programmed reaction(TPR) technique. On the temperature programmed studies, the effects of amounts of cerium and zirconium on the re-oxidation rate of partial reduced iron oxides were increased with increasing metal additives amount, but the rhodium amount showed little effect on the re-oxidation rate. On the thermal studies, the re-oxidation rates were enhanced with increasing temperature(300 $^{\circ}C$ < 350 $^{\circ}C$).

• 한국진공학회지
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• 제6권S1호
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• pp.96-109
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• 1997

In order to simulate the corrosion behavior of Zr-4 alloy in pressurized water reactors it was implanted (or bombarded) with 190ke V $Zr^+\; and \;Ar^+$ ions at liquid nitrogen temperature and room temperature respectively up to a dose of $5times10^{15} \sim 8\times10^{16} \textrm{ions/cm}^2$ The oxidation behavior and electrochemical vehavior were studied on implanted and unimplanted samples. The oxidation kinetics of the experimental samples were measured in pure oxygen at 923K and 133.3Pa. The corrosion parameters were measured by anodic polarization methods using a princeton Applied Research Model 350 corrosion measurement system. Auger Electron Spectroscopy (AES) and X-ray Photoelectric Spectroscopy (XPS) were employed to investigate the distribution and the ion valence of oxygen and zirconium ions inside the oxide films before and after implantation. it was found tat: 1) the $Zr^+$ ion implantation (or bombardment) enhanced the oxidation of Zircaloy-4 and resulted in that the oxidation weight gain of the samples at a dose of $8times10^{16}\textrm{ions/cm}^2$ was 4 times greater than that of the unimplantation ones;2) the valence of zirconium ion in the oxide films was classified as $Zr^0,Zr^+,Zr^{2+},Zr^{3+}\; and \;Zr^{4+}$ and the higher vlence of zirconium ion increased after the bombardment ; 3) the anodic passivation current density is about 2 ~ 3 times that of the unimplanted samples; 4) the implantation damage function of the effect of ion implantation on corrosion resistance of Zr-4 alloy was established.

• Nuclear Engineering and Technology
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• 제42권2호
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• pp.193-202
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• 2010

In order to study the cladding properties of zirconium after a loss-of-coolant accident (LOCA)-simulation oxidation and water quenching test, commercial Zircaloy-4 and two kinds of HANA claddings were oxidized at temperatures ranging from $900^{\circ}C$ to $1250^{\circ}C$ and exposed for 300 s, and then cooled to $700^{\circ}C$ before quenching. Microstructural observations were made to evaluate the matrix characteristics with the chemical compositions after the LOCA-simulation test. Ring compression testing was then performed to compare the ductile behaviour of the HANA and Zircaloy-4 claddings. An X-ray diffraction (XRD) analysis was carried out for temperatures ranging from room temperature to $1250^{\circ}C$ for the oxide layer to verify the oxide crystal structure at each oxidation temperature.

• The Journal of Advanced Prosthodontics
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• 제5권4호
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• pp.448-451
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• 2013

PURPOSE. Translucency of all-ceramic restorations is an important factor which affects the final appearance and esthetic outcome of the restoration. The aim of this study was to evaluate the effect of the shade of coloring liquid on the translucency of zirconia framework. MATERIALS AND METHODS. Thirty zirconium oxide core plate ($15{\times}12{\times}0.5$ mm) were divided into 6 groups of 5 plates each. Each group was classified according to the shade of coloring liquid based on Vita Classic Scale (A2, A3, B1, C2, and D2), and each sample was immersed in coloring liquid for 3 seconds as recommended by the manufacturer, except for the control group. Contrast ratio, as a translucency parameter, was calculated using a spectrophotometer and the data were analyzed with oneway analysis of variance (ANOVA) and Tukey's honestly significant differences (HSD) tests (${\alpha}$=.05). RESULTS. Significant differences in translucency among the control and test groups, and the B1 shaded group and other shades was observed. There were no significant differences among A2, A3, C2, and D2 shaded groups. CONCLUSION. The translucency of the zirconium oxide cores was affected by the coloring procedure and significant differences in the translucency measurements were identified between specific shades.

• Bulletin of the Korean Chemical Society
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• 제28권8호
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• pp.1341-1345
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• 2007

The surface chemistry of D2O dosed Zircaloy-4 (Zry-4) surface followed by Ar-ion bombardment and annealing was studied by means of X-ray photoelectron spectroscopy (XPS) and Ultraviolet photoelectron spectroscopy (UPS). In the XPS study, Ar-ion bombardment caused decrease of the oxygen on the surface region of Zry-4 and therefore led to change the oxidation states of the zirconium from oxide to metallic form. In addition, oxidation states of zirconium were changed to lower oxidation states of zirconium due to depopulation of oxygen on the surface region by annealing. Up to about 787 K, the bulk oxygen diffused out to the subsurface region and after this temperature, the oxygen on the surface of Zry-4 was depopulated. UPS study showed that the valence band spectrum of the D2O exposed Zry-4 exhibited a dominant peak at around 13 eV and no clear Fermi edge was detected. After stepwise Ar+ sputtering processes, the decrease of the oxygen on the surface of Zry-4 led to suppress the dominant peak around 13 eV, the peak around 9 eV and develop a new peak of the metallic Zr 4d state (20.5-21.0 eV) at the Fermi level.

• 한국결정성장학회지
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• 제29권4호
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• pp.154-159
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• 2019

용융 온도를 낮추고 균질화에 영향을 줄 수 있는 yttrium oxide(산화 이트륨)과 iron oxide(산화철)를 사용하여 $LI_2O-Al_2O_3-SiO_2$ 계 결정화 유리를 제조하였다. 조핵제는 Zirconium sulfate(황산지르코늄)을 사용했고, 유리 점도를 낮추기 위해 calcium phosphate(인산칼슘)을 사용해 유리 유동성을 원활하게 하였다. 결정화 유리는 열충격 $750^{\circ}C$ 이상을 만족했고, $800^{\circ}C$ 이상에서 열팽창계수가 급격하게 상승하는 온도를 약 $30^{\circ}C$ 이상 시프트 하였다. 따라서 yttrium oxide와 iron oxide 포함하는 LAS 계 유리는 고온에서 양호한 용융 상태와 우수한 열팽창 저항성을 확인하였고 특수 주방용 재료 분야에 충분히 활용이 가능하리라 판단되었다.

• 대한치과보철학회지
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• 제48권4호
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• pp.251-258
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• 2010

연구 목적: 이 연구의 목적은 표면처리방법이 지르코니아와 네 종류의 시멘트의 전단결합 강도에 미치는 영향을 평가하는 것이다. 연구 재료 및 방법: 총 120개의 디스크 모양의 산화 지르코늄 (3Y-TZP, Kyoritsu, Tokyo, Japan) 시편을 다음과 같이 표면처리 하였다: (1) $110\;{\mu}m$ 산화 알루미나 분사처리 (2) Silica coating ($Rocatec^{TM}$ 3M ESPE)를 이용한 표면처리 (3) 처리하지 않음. 각각의 표면 처리 후, 2종의 자가 접착형 시멘트 (RelyX Unicem, Maxcem)와 레진 강화 글라스 아이오노머 시멘트 (RelyX Luting), Bis-GMA 레진 시멘트 (Nexus3)를 시편에 부착하였으며 각 군은 UTM을 이용하여 전단결합강도를 측정하였다. 표면처리, 시멘트의 종류에 따른 결합강도의 차이를 살펴보기 위하여 일원변량분석 (One-way ANOVA)과 이원변량분석 (two-way ANOVA)을 이용하고 사후 분석으로 Tukey HSD test를 실시하였다. 결과: 로카텍 처리 후, RelyX Unicem을 부착한 군이 가장 높은 결합 강도를 보였으며 (P<.05) 알루미나 분사처리를 한 군과 로카텍 처리를 한 군은 아무런 처리를 하지 않은 군보다 유의하게 높은 결합 강도를 보였다 (P<.05). 또한 모든 표면상태에서 RelyX Luting은 다른 군에 비해 통계적으로 유의하게 가장 낮은 결합강도를 보였다 (P<.05). 결론: 본 연구의 결과에 따르면 RelyX Unicem은 지르코니아와 강한 결합력을 보였으며 로카텍 처리는 결합을 증진시키는데 효과적이었다.

• Corrosion Science and Technology
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• 제14권6호
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• pp.301-312
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• 2015

Corrosion of zirconium fuel cladding is known to limit the lifetime and reloading cycles of fuel in nuclear reactors. Oxide layers formed on ZIRLO4^{TM}$ cladding samples, after immersion for 300-hour and 50-day in a simulated primary water chemistry condition ($360^{\circ}C$ and 20 MPa), were analyzed by using the scanning transmission electron microscopy (STEM), in-situ transmission electron microscopy (in-situ TEM) with the focused ion beam (FIB) technique, and X-ray diffraction (XRD). Both samples (immersion for 300 hours and 50 days) revealed the presence of the ZrO sub-oxide phase at the metal/oxide interface and columnar grains developed perpendicularly to the metal/oxide interface. Voids and micro-cracks were also detected near the water/oxide interface, while relatively large lateral cracks were found just above the less advanced metal/oxide interface. Equiaxed grains were mainly observed near the water/oxide interface.