• Title/Summary/Keyword: U-10Zr

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질소 유량 변화에 따른 Zirconium Nitride의 Nano-electrotribology 특성변화 연구

  • Kim, Seong-Jun;Park, Myeong-Jun;Kim, Su-In;Lee, Chang-U
    • Proceedings of the Korean Vacuum Society Conference
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    • 2014.02a
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    • pp.355.1-355.1
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    • 2014
  • Zirconium nitride (ZrN)는 높은 녹는점과 기계적 강도 그리고 내식성을 가져 부품 산업계에서 hard coating에 이용된다. 또한 금속과 같은 전기 전도성을 가지므로 초고집적소자의 확산방지막에 이르기까지 많은 응용이 되고 있다. 본 실험에서는 Si 기판 위에rf magnetron sputter를 사용하여 Zr박막을 증착 하였으며 질소 유량을 변화시키며 Zirconium nitride 박막을 증착하였다. 증착된 박막의 질소 유량변화에 따른 nano-electrotribology 특성변화를 관찰하기 위해 nano-indenter를 사용하였다. 또한 Weibull statistics을 사용하여 박막의 균일성을 검증하였다. 질소 유량이 각각 0, 0.5, 5 sccm으로 증가하는 동안 surface hardness는 12.37, 10.49, 12.14 GPa로 변화하였다. 이때, 박막의 elastic modulus는 175.27, 163.94, 172.18 GPa로 각각 변화하였다. 이러한 결과는 질소 유량에 따라zirconium nitride가 여러 상으로 생성되는 것으로 해석할 수 있다.

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Determination of La in $U_3Si/Al$ Spent Nuclear Fuel by Ion Chromatography-Inductively Coupled Plasma-Mass Spectrometry (Ion Chromatography-Inductively Coupled Plasma-Mass Spectrometry에 의한 $U_3Si/Al$ 사용후핵연료 중 La의 분리 및 정량)

  • Han, Sun Ho;Choi, Kwang Soon;Kim, Jung Suk;Jeon, Young Shin;Park, Yang Soon;Jee, Kwang Yong;Kim, Won Ho
    • Analytical Science and Technology
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    • v.13 no.5
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    • pp.601-607
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    • 2000
  • Lanthanum has been used as one of the burnup monitor in spent nuclear fuel. $U_3Si/Al$ spent nuclear fuel contains small amount of La in high concentration of U and Al. Therefore, chemical separation of La is required to remove matrix elements. At first, ion chromatography (IC) and inductively coupled plasma systems were installed in radiation shielded glove box to handle the radioactive samples. Retention behavior of uranium, aluminum, lanthanum and some interesting fission products (Sr, Zr, Y, Mo, Ru, Pd, Rh, Cs, Ba, Ce, Pr, Nd, Sm, Eu and Cd) was investigated using the CG10 column and ${\alpha}$-HiBA eluent. As all elements were eluted earlier than lanthanum in 0.2 M ${\alpha}$-HiBA eluent, a portion of U and Al was directly passed to waste using a three way valve between the column and the nebulizer. Thus it was possible to determine the lanthanum in a high concentration of U and Al matrix. Retention time of La was about 12 minutes in this separation condition. Optimum range for the determination of La in $U_3Si/Al$ spent nuclear fuel was $1-10{\mu}g/L$ (ppb) with this system and detection limit was $0.25{\mu}g/L$ in case of $200{\mu}L$ of sample volume.

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Structural and Dielectric Properties of Pb[(Zr,Sn)Ti]NbO3 Thin Films Deposited by Radio Frequency Magnetron Sputtering

  • Choi, Woo-Chang
    • Transactions on Electrical and Electronic Materials
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    • v.11 no.4
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    • pp.182-185
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    • 2010
  • $Pb_{0.99}[(Zr_{0.6}Sn_{0.4})_{0.9}Ti_{0.1}]_{0.98}Nb_{0.02}O_3$ (PNZST) thin films were deposited by radio frequency magnetron sputtering on a $(La_{0.5}Sr_{0.5})CoO_3$ (LSCO)/Pt/Ti/$SiO_2$/Si substrate using a PNZST target with an excess PbO of 10 mole%. The thin films deposited at the substrate temperature of $500^{\circ}C$ crystallized to a perovskite phase after rapid thermal annealing (RTA). The thin films, which annealed at $650^{\circ}C$ for 10 seconds in air, exhibited good crystal structures and ferroelectric properties. The remanent polarization and coercive field of the fabricated PNZST capacitor were approximately $20uC/cm^2$ and 50 kV/cm, respectively. The reduction of the polarization after $2.2\;{\times}\;10^9$ switching cycles was less than 10%.

Reprocessing of fluorination ash surrogate in the CARBOFLUOREX process

  • Boyarintsev, Alexander V.;Stepanov, Sergei I.;Chekmarev, Alexander M.;Tsivadze, Aslan Yu.
    • Nuclear Engineering and Technology
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    • v.52 no.1
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    • pp.109-114
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    • 2020
  • This work presents the results of laboratory scale tests of the CARBOFLUOREX (CARBOnate FLUORide EXtraction) process - a novel technology for the recovery of U and Pu from the solid fluorides residue (fluorination ash) of Fluoride Volatility Method (FVM) reprocessing of spent nuclear fuel (SNF). To study the oxidative leaching of U from the fluorination ash (FA) by Na2CO3 or Na2CO3-H2O2 solutions followed by solvent extraction by methyltrioctylammonium carbonate in toluene and purification of U from the fission products (FPs) impurities we used a surrogate of FA consisting of UF4 or UO2F2, and FPs fluorides with stable isotopes of Ce, Zr, Sr, Ba, Cs, Fe, Cr, Ni, La, Nd, Pr, Sm. Purification factors of U from impurities at the solvent extraction refining stage reached the values of 104-105, and up to 106 upon the completion of the processing cycle. Obtained results showed a high efficiency of the CARBOFLUOREX process for recovery and separating of U from FPs contained in FA, which allows completing of the FVM cycle with recovery of U and Pu from hardly processed FA.

High Mobility, High Work Function 특성을 가지는 ITZO의 박막 분석과 실리콘 이종접합 태양전지 적용에 관한 연구

  • An, Si-Hyeon;Kim, Seon-Bo;Jang, Ju-Yeon;Jang, Gyeong-Su;Park, Hyeong-Sik;Song, Gyu-Wan;Choe, U-Jin;Choe, Jae-U;Lee, Jun-Sin
    • Proceedings of the Korean Vacuum Society Conference
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    • 2012.02a
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    • pp.601-601
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    • 2012
  • 본 연구는 Zr이 doping된 ITO target (ITO:Zr)을 $200^{\circ}C$ 이하의 낮은 온도에서 RF magnetron sputtering을 이용한 증착으로 high mobility, high workfunction의 TCO 박막을 제작하고 이를 실리콘 이종접합 태양전지의 front TCO 적용에 관한 연구이다. 상기 공정으로 제작된 ITZO 박막의 가장 낮은 비저항은 $2.58{\times}10-4{\Omega}-cm$이며 이때의 투과도는 90%를 얻을 수 있었다. 또한 기존의 TCO로 사용되던 AZO 및 ITO보다 높은 work function으로 인하여 태양전지의 front TCO 적용시 710 mV 이상의 개방 전압 상승과 band-offset 감소에 따른 34.44 mA 이상의 단락전류 상승을 얻을 수 있었다. 또한 높은 mobility에 의한 면저항 감소로 충진률 상승도 얻을 수 있었다. 상기 인자에 대한 태양전지 특성의 변화는 quantum efficiency 분석으로 규명할 수 있었다.

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FAST irradiations and initial post irradiation examinations - Part I

  • G. Beausoleil;L. Capriotti;B. Curnutt;R. Fielding;S. Hayes;D. Wachs
    • Nuclear Engineering and Technology
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    • v.54 no.11
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    • pp.4084-4094
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    • 2022
  • The Advanced Fuels Campaign Fission Accelerated Steady-state Test (FAST) at Idaho National Laboratory (INL) completed its first irradiation cycle within the Advanced Test Reactor (ATR). The test focused on the irradiation of alloy fuel forms for use in sodium fast reactors. The first cycle of FAST testing was completed and four rodlets were removed for the initial post irradiation examination (PIE). The rodlet design and irradiation conditions were evaluated using Monte Carlo N-Particle (MCNP) for as-run power history and COMSOL for temperature analysis. These rodlets include a set of low burnups (~2.5 % fissions per initial metal atoms [%FIMA]), control rodlets, and a helium-bonded annular rodlet (4.7 %FIMA). Nondestructive PIE has been completed and includes visual inspection, neutron radiography and gamma scanning of the FAST capsules and rodlets. Radiography confirmed the integrity of the experiments, revealed that the annulus in the annular fuel was filled at a modest burnup (4.7 %FIMA), and indicated potential slumping of the cooler rodlets at lower burnup. Precision gamma scanning indicated mostly usual fission product behavior, except for cesium in the He-bonded annular fuel. Future destructive PIE will be necessary to fully interpret the effects of accelerated irradiation on U-Zr metallic fuel behavior.

Effect of Surface Condition on the Bonding Characteristics of 3Y-$ZrO_2$-Metal Bracket System (3Y-$ZrO_2$ 세라믹과 교정용 브라켓계에서 세라믹의 표면 조건에 따른 접착 거동의 변화)

  • O, Seon-Mi;Kim, Jin-Seong;Lee, Chae-Hyun
    • Journal of Technologic Dentistry
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    • v.33 no.1
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    • pp.47-54
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    • 2011
  • Purpose: To investigate shear bonding strength between dental zirconia ceramics with different surface treatment and metal bracket. Methods: Zirconia ceramics(LAVA, 3M ESPE, USA) were divided to 4 groups according to their surface treatment; no surface treatment(G1), sand blasting(G2), silane coating(G3), and sand blasting+silane coating(G4). Specimens were bonded to metal bracket using resin bond($Transbond^{TM}XT$, 3M Unitek, USA). Shear bond strength was measured using universal test machine(3366 INSTRON. U.S.A) with cross head speed of 1 mm/min. Microstructural investigation for fracture surface was performed after shear test. Results: Shear bonding strengths of single surface treatment groups (G2 and G3) were higher than no treatment group(G1). Combined Treatment Group (G4) showed the highest shear bond strength of 9.15MPa. Microstructural observation shows that higher shear bonding strength was obtained when debonding was occurred at metal bracket/resin interface rather than zirconia ceramic/resin interface. Conclusion: Surface treatment of zirconia is necessary to obtain higher bonding strength. Combined treatment can be more effective when surface the surfaces are kept clean and homogeneous.

The Effect of Magnetic Field on Enhancing the Anisotropy of Melt-spun Nd-Fe-Co(-Zr)-B Alloy (급속응고중 외부자장에 의한 Nd-Fe-Co(-Zr)-B계 합금의 자기이방성 향상)

  • Lee, U-Yeong;Choe, Seung-Deok;Yang, Chung-Jin
    • Journal of the Korean Magnetics Society
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    • v.2 no.3
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    • pp.233-238
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    • 1992
  • Melt-spun $Nd_{14}Fe_{76}Co_4B_6$ and $Nd_{10.5}Fe_{79}Co_2Zr_{1.5}B_7$ ribbons were prepared under an externally applied magnetic field. Magnetic properties in terms of anisotropy were evaluated by discussing the effect of textured structure of the ribbon samples as well as its powders. About 32 % increase in $(B{\cdot}H)_{max}$ and 18.8 % increase in $B_r$ were observed along the perpendicular direction of the ribbon plane which is more prominent for the Nd-Fe-Co-Zr-B than for the Nd-Fe-Co-B alloy. The enhancement of magnetic anisotropy was monitored by measuring the anisotropy constant of each alloy as a function of quenching rate of the ribbon. It was found that for the melt-spun ribbon quenched at slow rate(less than 7 m/s) the magnetic field effect was overwhelmed by the heat gradient effect through the ribbon thickness while the field effect was prominent at intermediate quenching rate (more than 7~11 m/s). The reproducible maximum energy product, $(B{\cdot}H)_{max}$=16.4 MGOe can be obtained from the Nd-Fe-Co-Zr-B alloy.

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