• 제목/요약/키워드: Atomic configuration

검색결과 122건 처리시간 0.026초

상호 간섭이 최소화된 고속 원자현미경용 XY 스캐너 제작 (An XY scanner with minimized coupling motions for the high speed AFM)

  • 박종규;문원규
    • 한국정밀공학회:학술대회논문집
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    • 한국정밀공학회 2005년도 춘계학술대회 논문집
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    • pp.653-656
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    • 2005
  • This paper introduces design, fabrication and experiment process of a novel scanner for the high speed AFM(Atomic Force Microscope). A proper design modification is proposed through analyses on the dynamic characteristics of the existing linear motion stages using a dynamic analysis program, Recurdyn. Since the scanning speed of each direction is allowed to be different, the linear motion stage for the high-speed scanner of AFM can be so designed to have different resonance frequencies for the modes with one dominant displacement in the desired directions. One way to achieve this objective is to use one-direction flexure mechanism for each direction and to mount one stage for fast motion on the other stage for slow motion. This unsymmetrical configuration separates the frequencies of the two vibration modes with one dominant displacement in each desired direction, hence, the coupling between the motions in the two directions. In addition, a pair of actuators is used for each axis to decrease the cross talks in the two motions and gives a force large enough to actuate the slow motion stage, which carries the fast motion stage. After these design modifications, a novel scanner with scanning speed higher than 10 Hz can be achieved to realize undistorted images in the high speed AFM.

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Neutron Streaming and PWR Cavity Shielding Design

  • Kim, Kyo-Sool;Lee, Chang-Kun
    • Nuclear Engineering and Technology
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    • 제12권2호
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    • pp.127-134
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    • 1980
  • 최근 가압경수로에서 압력용기 상단주변의 캐비티에 중성자가 새어나오는 사실이 판명되자 이에 대한 차폐문제가 심각하게 논의되기 시작했다. 본 논문에서는 현재 운전중인 원자로에서 이것을 어떻게 해결하고 있는가를 예시하였다. 예를들면 붕소가 들어있는 주머니를 쌓아 올리는 것에서부터 화폐구조물을 영구히 설치하는 것에 이르기까지 여러가지 방법으로 중성자흐름을 막는 대책을 논의하였다. 결론적으로 이 문제해결을 위한 가장 현실적이고 가능한 차폐설계안 몇가지를 제시하였다. 특히 그중에서도 중성자가 어떤 경로로 흘러 나오는가의 규명. 차폐자료의 선정, 차폐설계의 특성과 외형문제 그리고 각 설계안을 검토키 위한 수학적 모델 제시에 역점을 두었다.

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인가 자기장에 의한 YBCO 초전도체 복합체의 포획 자기장 특성 (The Trapped Field Characteristics of YBCO Superconductor Composite in Terms of Applied Magnetic Field)

  • 이만수;장건익;최연석;전병혁;한영희;박병준
    • Progress in Superconductivity
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    • 제12권1호
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    • pp.12-16
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    • 2010
  • We have measured the trapped field of YBCO bulk with different configuration by applying the magnetic field of $Nb_3Sn$ superconducting magnet. Initially the circular type of YBCO bulk superconductor was prepared and then hole, parallel to the c-axis and located at the center of bulk was mechanically drilled. The YBCO bulk with hole was filled with resin. Typical size of hole in YBCO bulk was 10 mm in diameter. Trapped field characteristics were compared with different specimen conditions. Our preliminary result indicates the increment rate of trapped field, 0.232 kG, measured on the YBCO without hole was much higher than that, 0.011 kG, measured on YBCO with hole.

Quantitative observation of co-current stratified two-phase flow in a horizontal rectangular channel

  • Lee, Seungtae;Euh, Dong-Jin;Kim, Seok;Song, Chul-Hwa
    • Nuclear Engineering and Technology
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    • 제47권3호
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    • pp.267-283
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    • 2015
  • The main objective of this study is to investigate experimentally the two-phase flow characteristics in terms of the direct contact condensation of a steam-water stratified flow in a horizontal rectangular channel. Experiments were performed for both air-water and steam-water flows with a cocurrent flow configuration. This work presents the local temperature and velocity distributions in a water layer as well as the interfacial characteristics of both condensing and noncondensing fluid flows. The gas superficial velocity varied from 1.2 m/s to 2.0 m/s for air and from 1.2 m/s to 2.8 m/s for steam under a fixed inlet water superficial velocity of 0.025 m/s. Some advanced measurement methods have been applied to measure the local characteristics of the water layer thickness, temperature, and velocity fields in a horizontal stratified flow. The instantaneous velocity and temperature fields inside the water layer were measured using laser-induced fluorescence and particle image velocimetry, respectively. In addition, the water layer thickness was measured through an ultrasonic method.

Evaluations of Sb20Se80-xGex (x = 10, 15, 20, and 25) Glass Stability from Thermal, Structural and Optical Properties for IR Lens Application

  • Jung, Gun-Hong;Kong, Heon;Yeo, Jong-Bin;Lee, Hyun-Yong
    • 한국세라믹학회지
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    • 제54권6호
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    • pp.484-491
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    • 2017
  • Chalcogenide glasses have been investigated in their thermodynamic, structural, and optical properties for application in various opto-electronic devices. In this study, the $Sb_{20}Se_{80-x}Ge_x$ with x = 10, 15, 20, and 25 were selected to investigate the glass stability according to germanium ratios. The thermal, structural, and optical properties of these glasses were measured by differential scanning calorimetry (DSC), X-ray diffraction (XRD), and UV-Vis-IR Spectrophotometry, respectively. The DSC results revealed that $Ge_{20}Sb_{20}Se_{60}$ composition showing the best glass stability theoretically results due to a lower glass transition activation energy of 230 kJ/mol and higher crystallization activation energy of 260 kJ/mol. The structural and optical analyses of annealed thin films were carried out. The XRD analysis reveals obvious results associated with glass stabilities. The values of slope U, derived from optical analysis, offered information on the atomic and electronic configuration in Urbach tails, associated with the glass stability.

이중층 탄소나노튜브 전계전자 방출원의 신뢰성 있는 전계방출 특성 (A Reliable Field Emission Performance of Double-Walled Carbon Nanotube Field Emitters)

  • 정승일;이승백
    • 한국진공학회지
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    • 제17권6호
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    • pp.566-575
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    • 2008
  • 촉매 화학기상증착법을 이용하여 합성된 이중층 탄소나노튜브를 가지고 전계전자 방출원을 제작하여 이들의 신뢰성 있는 전계전자 방출특성을 조사하였다. 합성된 탄소 필라멘트들은 TEM, TGA, 그리고 Raman 분석을 통하여 결함이 없고 순도가 높은 이중층 탄소나노튜브가 합성이 되었음을 확인하였다. 이들 이중층 탄소나노튜브 전계전자 방출원은 이전극 구조에서 낮은 턴-온 전계와 높은 전류밀도의 전계전자 방출 특성을 보여주었고, 균질한 전계방출 패턴과 좋은 전계방출 안정성을 나타내었다.

Uncertainty analysis of ROSA/LSTF test by RELAP5 code and PKL counterpart test concerning PWR hot leg break LOCAs

  • Takeda, Takeshi;Ohtsu, Iwao
    • Nuclear Engineering and Technology
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    • 제50권6호
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    • pp.829-841
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    • 2018
  • An experiment was conducted for the OECD/NEA ROSA-2 Project using the large-scale test facility (LSTF), which simulated a 17% hot leg intermediate-break loss-of-coolant accident in a pressurized water reactor (PWR). In the LSTF test, core uncovery started simultaneously with liquid level drop in crossover leg downflow-side before loop seal clearing, and water remaining occurred on the upper core plate in the upper plenum. Results of the uncertainty analysis with RELAP5/MOD3.3 code clarified the influences of the combination of multiple uncertain parameters on peak cladding temperature within the defined uncertain ranges. For studying the scaling problems to extrapolate thermal-hydraulic phenomena observed in scaled-down facilities, an experiment was performed for the OECD/NEA PKL-3 Project with the Primarkreislaufe Versuchsanlage (PKL), as a counterpart to a previous LSTF test. The LSTF test simulated a PWR 1% hot leg small-break loss-of-coolant accident with steam generator secondary-side depressurization as an accident management measure and nitrogen gas inflow. Some discrepancies appeared between the LSTF and PKL test results for the primary pressure, the core collapsed liquid level, and the cladding surface temperature probably due to effects of differences between the LSTF and the PKL in configuration, geometry, and volumetric size.

The effect of cooling rates on carbide precipitate and microstructure of 9CR-1MO oxide dispersion strengthened(ODS) steel

  • Jang, Ki-Nam;Kim, Tae-Kyu;Kim, Kyu-Tae
    • Nuclear Engineering and Technology
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    • 제51권1호
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    • pp.249-256
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    • 2019
  • The 9Cr-1Mo ferritic-martensitic ODS steel is a promising structural material for the next generation nuclear power plants including fast reactors for application in reactor vessels and nuclear fuel. The ODS steel was cooled down by furnace cooling, air cooling, oil quenching and water quenching, respectively, after normalizing it at $1150^{\circ}C$ for 1 h and then tempering at $780^{\circ}C$ for 1 h. It is found that grain size, a relative portion of ferrite and martensite, martensitic lath configuration, behaviors of carbide precipitates, and hardness of the ODS steel are strongly dependent on a cooling rate. The grain size and martensitic lath width become smaller with the increase in a cooling rate. The carbides were precipitated at the grain boundaries formed between the ferrite and martensite phases and at the martensitic lath interfaces. In addition, the carbide precipitates become smaller and more widely dispersed with the increase in a cooling rate, resulting in that the faster cooling rate generated the higher hardness of the ODS steel.

Graph neural network based multiple accident diagnosis in nuclear power plants: Data optimization to represent the system configuration

  • Chae, Young Ho;Lee, Chanyoung;Han, Sang Min;Seong, Poong Hyun
    • Nuclear Engineering and Technology
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    • 제54권8호
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    • pp.2859-2870
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    • 2022
  • Because nuclear power plants (NPPs) are safety-critical infrastructure, it is essential to increase their safety and minimize risk. To reduce human error and support decision-making by operators, several artificial-intelligence-based diagnosis methods have been proposed. However, because of the nature of data-driven methods, conventional artificial intelligence requires large amount of measurement values to train and achieve enough diagnosis resolution. We propose a graph neural network (GNN) based accident diagnosis algorithm to achieve high diagnosis resolution with limited measurements. The proposed algorithm is trained with both the knowledge about physical correlation between components and measurement values. To validate the proposed methodology has a sufficiently high diagnostic resolution with limited measurement values, the diagnosis of multiple accidents was performed with limited measurement values and also, the performance was compared with convolution neural network (CNN). In case of the experiment that requires low diagnostic resolution, both CNN and GNN showed good results. However, for the tests that requires high diagnostic resolution, GNN greatly outperformed the CNN.

Comprehensive validation of silicon cross sections

  • Czakoj, Tomas;Kostal, Michal;Simon, Jan;Soltes, Jaroslav;Marecek, Martin;Capote, Roberto
    • Nuclear Engineering and Technology
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    • 제52권12호
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    • pp.2717-2724
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    • 2020
  • Silicon, especially silicon in the form of SiO2, is a major component of rocks. Final spent fuel storages, which are being designed, are located in suitable rock formations in the Earth's crust. Reduction of the uncertainty of silicon neutron scattering and capture is needed; improved silicon evaluations have been recently produced by the ORNL/IAEA collaboration within the INDEN project. This paper deals with the nuclear data validation of that evaluation performed at the LR-0 reactor by means of critical experiments and measurement of reaction rates. Large amounts of silicon were used both as pure crystalline silicon and SiO2 sand. The critical moderator level was measured for various core configurations. Reaction rates were determined in the largest core configuration. Simulations of the experimental setup were performed using the MCNP6.2 code. The obtained results show the improvement in silicon cross-sections in the INDEN evaluations compared to existing evaluations in major libraries. The new Thermal Scattering Law for SiO2 published in ENDF/B-VIII.0 additionally reduces the discrepancy between calculation and experiments. However, an unphysical peak is visible in the neutron spectrum in SiO2 obtained by calculation with the new Thermal Scattering Law.