• 제목/요약/키워드: Beryllium

검색결과 90건 처리시간 0.021초

베릴륨이 포함되지 않은 도재용착주조관용 비 귀금속 합금의 재사용에 따른 금속과 도재간의 전단결합강도에 관한 연구 (The study of Shear Bond Strength on recasting of non-beryllium non-precious alloy for Porcelain between Metal)

  • 김소리;김웅철;김혜영;김지환
    • 대한치과기공학회지
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    • 제35권1호
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    • pp.43-48
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    • 2013
  • Purpose: This study aimed to investigate the shear bond strength for non-precious alloy castings without beryllium, which has been used repeatedly for economical reason. Methods: The Schmitz-Schulmeyer test method was used to evaluate the shear bond strength between the non-beryllium Ni-Cr alloy Vera Bond 2V(AlbaDent, Inc. USA) and the Ceramco 3(Dentstply, York, PA, USA) porcelain powder. The maximum loading and shear bond strength were measured. The average shear strength(MPa) was analyzed with the one-way ANOVA and the Tukey's test( =.05). The fracture specimens were examined using Microscope to determine the failure pattern. Results: The mean shear bond strengths(SD) in MPa were group A(100% new metal) control 28.72(3.31); group B(50% new + 50% reused) 27.28(1.13); group C(all reused) 26.61(5.47). Microscope examination showed that group A and B specimens presented mixed failure, and group C specimens showed adhesive failure. Conclusion: In conclusion, forward this non-precious alloy dose not contain beryllium for how should use a more systematic study and for future advanced research is performed giving effect to be considered desirable.

Target-Moderator-Reflector system for 10-30 MeV proton accelerator-driven compact thermal neutron source: Conceptual design and neutronic characterization

  • Jeon, Byoungil;Kim, Jongyul;Lee, Eunjoong;Moon, Myungkook;Cho, Sangjin;Cho, Gyuseong
    • Nuclear Engineering and Technology
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    • 제52권3호
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    • pp.633-646
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    • 2020
  • Imaging and scattering techniques using thermal neutrons allow to analyze complex specimens in scientific and industrial researches. Owing to this advantage, there have been a considerable demand for neutron facilities in the industrial sector. Among neutron sources, an accelerator driven compact neutron source is the only one that can satisfy the various requirements-construction budget, facility size, and required neutron flux-of industrial applications. In this paper, a target, moderator, and reflector (TMR) system for low-energy proton-accelerator driven compact thermal neutron source was designed via Monte Carlo simulations. For 10-30 MeV proton beams, the optimal conditions of the beryllium target were determined by considering the neutron yield and the blistering of the target. For a non-borated polyethylene moderator, the neutronic properties were verified based on its thickness. For a reflector, three candidates-light water, beryllium, and graphite-were considered as reflector materials, and the optimal conditions were identified. The results verified that the neutronic intensity varied in the order beryllium > light water > graphite, the compacter size in the order light water < beryllium < graphite and the shorter emission time in the order graphite < light water < beryllium. The performance of the designed TMR system was compared with that of existing facilities and were laid between performance of existing facilities.

베릴륨 확산 처리 된 마다가스카르산 사파이어의 분광특성분석 (Spectroscopic Characteristics of Sapphire from Madagascar Diffused with Beryllium)

  • 정순희;안용길;서진교;박종완
    • 한국광물학회지
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    • 제22권2호
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    • pp.87-95
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    • 2009
  • 마다가스카르산 사파이어를 수평 알루미나 튜브의 전기로에서 대기중의 산화분위기 하에 $1650^{\circ}C$, 50시간의 조건으로 $Be^{2+}$의 확산 처리를 하였다. 자외선-가시광선 분광분석 결과는 각 시료 마다 차이는 있으나 전체적으로 $Fe^{2+}$에서 $Fe^{3+}$로 산화의 원인으로 청색이 옅어졌고 청자색 사파이어는 $Cr^{3+}$에 의한 분홍색이 나타났다. $Be^{2+}$의 확산 처리로 부분적인 갈색이 나타난 청색 사파이어에서는 진한 주황색 부분이 나타났고, 옥화메틸렌에 의한 침적실험 관찰 결과로 시료들의 가장자리에 주황색의 집중현상이 나타났음을 확인하였다. 또한 기존에 있던 내포물도 변화가 나타났다. 그러나 확산 처리 온도의 한계로 더 많은 양의 $Be^{2+}$의 확산이 이루어 지지는 못했다.

도재-금속보철물용(陶材-金屬補綴勿用) Ni-Cr계(系) 비귀금속합금(非貴金屬合金)의 주조성(鑄造性)에 관(關)한 연구(硏究) (A Study of castability of Nickel-Chromium Alloys for porcelain fused to meta system)

  • 김치영
    • 대한치과기공학회지
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    • 제8권1호
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    • pp.45-50
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    • 1986
  • This study investigated the effect of burnout temperature on the castability of some nickelchromium alloys for porcelain fused to metal system and the effect of beryllium on the castability. Four alloys were evaluated: two contained beryllium(rexillium III, Super I) and two nonberyllium(Unibond, NNB). five burnout temperature, ranging form 100$^{\circ}F$ to 1800$^{\circ}F$, were aet at 200$^{\circ}F$ intervals for this study. The results obtained were as follows: 1. Beryllium-containing alloys were more castable than nonberyllium-containing alloys. 2. There was an optimal burnout temperature of range from 1400$^{\circ}F$ to 1600$^{\circ}F$ for the berylliumcontaining alloys studied. 3. An optimal burnout temperature for the nonberyllium alloys was not established.

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Beryllium oxide utilized in nuclear reactors: Part II, A systematic review of the neutron irradiation effects

  • Ming-dong Hou;Xiang-wen Zhou;Bing Liu
    • Nuclear Engineering and Technology
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    • 제55권2호
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    • pp.408-420
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    • 2023
  • Beryllium oxide (BeO) is being re-emphasized and utilized in Micro Modular Reactors (MMR) because of its prominent nuclear and high temperature properties in recent years. The implications of the research about effects of neutron irradiation on the microstructure and properties of BeO are significant. This article comprehensively reviews the effects of neutron irradiation on BeO and proposes the maximum permissible neutron doses at different temperatures for BeO without cracks in appearance according to the data in the previous literature. This maximum permissible neutron dose value has important reference significance for the experimental study of BeO. The effects of neutron irradiation on the thermal conductivity and flexural strength of BeO are also discussed. In addition, microstructure evolution of irradiated BeO during post-irradiation annealing is summarized. This review article has important implications for the application of BeO in MMR.

베릴륨함유 치과 주조용 비귀금속 합금의 젖산용액에 의한 금속 노출수준 평가 (Evaluation of a metal level in non-precious metal alloys dental casting having beryllium by lactic acid Solution)

  • 박수철;장은진;한석윤
    • 대한치과기공학회지
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    • 제33권2호
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    • pp.121-128
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    • 2011
  • Purpose: The purpose of this study is to investigate the level of each metal in non-precious metal alloys dental casting, still used even banned for use and trade by the law, for oral health. Methods: Two kinds of metal alloys were analyzed. One was Ticonium 100 for removable prosthesis and the other was Rexillium V for dental porcelain. Two samples of each metal alloy were made in 0.5g, 1.0g, and 1.5g. Total number of samples were 12. Two kinds of lactic acid Solution, pH7 and pH4.6, were injected into each samples. After injection, each samples had been for 21days ${\pm}$ 1 hour in the water tank of which temperature was $37^{\circ}C$. The level of metal was measured in each sample by inductively couplled plasma-atomic emission spectrometer. Results: In both metal alloys, metals, chrome, nickel, beryllium, and molybdenum, were founded. In Ticonium 1000, the highest level of nickel was 2.531ppm in 1.5g pH4.6 sample while the highest level of nickel was 4.062ppm in 1.5g pH4.6 sample of Rexillium V. In chemical composition of these methal alloys, chrome(14~17%) was much more than beryllium(1.95~1.99%) and molybdenum(5.0~9.0%) but berllium and molybdenum were founded more than chrome in samples. Therefore, chrome showed better anti-corrosion than other metal alloys. In both metal alloys, more metals were founded in higher pH level and more mass. Levels of chrome was significantly different in samples of both metal alloys in each pH level(p<0.05). Levels of nickels was significantly different in samples of both metal alloys in each pH level(p<0.05). Conclusion: For oral health, further studies are needed in nickel-chrome metal alloy and cobalt metal alloy of non-beryllium in addittion to beryllium metal alloy and also long-term studies needed in various period and other non-percious metal alloys for dental casting.

극박판의 인장-드로잉 성형에서의 제품품질 비교 (Formability and Dimensional Characteristics of Stretch-Drawn Beryllium-Copper Sheet Products)

  • 이기성;정완진;김종호
    • 소성∙가공
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    • 제20권5호
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    • pp.357-361
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    • 2011
  • A beryllium copper alloy(C1720) sheet was stretch-drawn using different processes. A hemispherical punch was first used and the forming behavior was examined. Then, cylindrical cups with a hemispherical head were produced by either one-step drawing or two-step forming(sequential stretch forming-drawing). The one-step drawing showed the better formability than two-step forming. However, the two-step forming was the superior process in terms of attaining shape accuracy.

치과용 비귀금속합금의 식각표면에 대한 주사전자현미경적 연구 (Scanning Electron Micrographic Study on the Etched Surface of Base Metal Alloys for Dental Restorations)

  • 정헌영;이선형
    • 대한치과보철학회지
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    • 제23권1호
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    • pp.83-95
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    • 1985
  • The purpose of this study was to evaluate microstructures on the etched surface of 11 base metal alloys for dental restorations and to observe the relationship between the etching pattern and beryllium. For this purpose, the following experiments were done; 11 base metal alloys were etched in (1) 10% $H_2SO_4$, (2) 10% $H_2SO_4$, 9 parts+methanol 1 part (3) Conc. $HNO_3$ 25%+glacial acetic acid 25%+$H_2O$ 50% (4) Conc. $HNO_3$ 5% (5) 2% glacial acetic acid added to Conc. $HNO_3$ 1% solution, with their etching conditions varied. Etched surface of alloys were examined under the scanning electron microscope. Results were as follows; 1. Almost all of Ni-Cr-Be alloys showed gooed etchd surface in $H_2SO_4$, solution, while some of those alloys which contains no beryllium showed good etched surface in $HNO_3$ solution. 2. Main components of etching solution can vary etching pattern of alloys. 3. Gamma prime phase relief, which can be found in all Ni-Cr-Be alloys, can't be found in any alloy that contains no beryllium.

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핵 융합로 제1벽의 냉각성능에 관한 수치해석적 연구 (Numerical analysis of the cooling effects for the first wall of fusion reactor)

  • 정인수;황영규
    • 설비공학논문집
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    • 제11권1호
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    • pp.18-30
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    • 1999
  • A heat transfer analysis for the two-dimensional (2-D) steady state using finite difference method (FDM) is performed to predict the thermal behavior of the primary first-wall (FW) system of fusion reactor under various geometric and thermo-hydraulic conditions, such as the beryllium (Be) armor thickness, pitch of cooling tube, and coolant velocity. The FW consists of authentic steel (type 316 stainless steel solution annealed) for cooling tubes, Cu for cooling tubes embedding material, and Be for a protective armor, based on the International Thermonuclear Experiment Reactor (ITER) report. The present 2-D analysis, the control volume discretized with hybrid grid (rectangular grid and polar grid) and Gauss-Seidel iteration method are adapted to solve the governing equations. In the present study, geometric and thermo-hydraulic parameters are optimized with consideration of several limitations. Consequently, it is suggested that the adequate pitch of cooling tube is 22-32mm, the beryllium armor thickness is 10-12mm, and that the coolant velocity is 4.5m/s-6m/s for $100^{\circ}C$ of inlet coolant temperature. The cooling tube should locate near beryllium armor. But, it would be better for locating the center of Cu wall, considering problems of material and manufacturing. Also, 2-D analysis neglecting the axial temperature distribution of cooling tube is appropriate, regarding the discretization error in axial direction.

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Neutron activation analysis: Modelling studies to improve the neutron flux of Americium-Beryllium source

  • Didi, Abdessamad;Dadouch, Ahmed;Jai, Otman;Tajmouati, Jaouad;Bekkouri, Hassane El
    • Nuclear Engineering and Technology
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    • 제49권4호
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    • pp.787-791
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    • 2017
  • Americium-beryllium (Am-Be; n, ${\gamma}$) is a neutron emitting source used in various research fields such as chemistry, physics, geology, archaeology, medicine, and environmental monitoring, as well as in the forensic sciences. It is a mobile source of neutron activity (20 Ci), yielding a small thermal neutron flux that is water moderated. The aim of this study is to develop a model to increase the neutron thermal flux of a source such as Am-Be. This study achieved multiple advantageous results: primarily, it will help us perform neutron activation analysis. Next, it will give us the opportunity to produce radio-elements with short half-lives. Am-Be single and multisource (5 sources) experiments were performed within an irradiation facility with a paraffin moderator. The resulting models mainly increase the thermal neutron flux compared to the traditional method with water moderator.