• Title/Summary/Keyword: flux guide

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Design and Fabrication of 2-T Rotating Halbach Magnet for Magnetic Refrigerator

  • Ryu, Kwon Sang;Nahm, Seung Hoon;Jung, Jae Kap;Baek, Seung-Wook
    • Journal of Magnetics
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    • v.22 no.1
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    • pp.65-68
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    • 2017
  • This paper reports simulation and evaluation of the magnetic flux density (MFD) of a rotating Halbach magnet (RHM) composed of a rotating inner Halbach cylinder (HC) and a fixed outer HC. We first chose the dimension of a single HC, then determined the dimensions of an inner and outer HC to get MFD = 2 T. Simulation results were used to guide fabrication of an RHM; its magnetic field in the central axis direction agreed well with simulated values.

EVALUATION OF FAST NEUTRON FLUENCE FOR KORI UNIT 3 PRESSURE VESSEL

  • Yoo, Choon-Sung;Kim, Byoung-Chul;Chang, Kee-Ok;Lee, Sam-Lai;Park, Jong-Ho
    • Nuclear Engineering and Technology
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    • v.38 no.7
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    • pp.665-674
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    • 2006
  • Three-dimensional neutron flux and fluence of Kori Unit 3 were evaluated using the synthesis technique described in Regulatory Guide 1.190 for all reactor geometry. For this purpose DORT neutron transport calculations from Cycle 1 to Cycle 15 were performed using BUGLE-96 cross-section library. The calculated flux and fluence were validated by comparing the calculated reaction rates to the measurement data from the dosimetry sensor set of the $5^{th}$ surveillance capsule withdrawn at the end of cycle 15 of Kori Unit 3. And then the best estimation of the neutron exposures for the reactor vessel beltline region was performed using the least square evaluation. These results can be used in the assessment of the state of embrittlement of Kori Unit 3 pressure vessel.

Numerical study of topological SQUIDs

  • Soohong, Choi;Yeongmin, Jang;Sara, Arif;Yong-Joo, Doh
    • Progress in Superconductivity and Cryogenics
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    • v.24 no.4
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    • pp.11-15
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    • 2022
  • We conducted numerical calculations to obtain the critical current as a function of the magnetic flux through the topologically trivial and non-trivial superconducting quantum interference devices (SQUIDs), with varying the capacitive and inductive couplings of Josephson junctions (JJs). Our calculation results indicate that a nontrivial SQUID is almost indistinguishable from trivial SQUID, considering the effective capacitance coupling. When the SQUID contains 2π- and 4π-periodic supercurrents, the periodicity of the current-flux relation can be distinguished from the purely trivial or nontrivial SQUID cases, and its difference is sensitive to the relative ratio between the topologically trivial and nontrivial supercurrents. We believe that our calculation results would provide a practical guide to quantitatively measure the portion of the topologically nontrivial supercurrents in experiments.

Illuminance Distribution and Photosynthetic Photon Flux Density Characteristics of LED Lighting with Periodic Lattice Arrangements

  • Jeon, Hee-Jae;Ju, Kang-Sig;Joo, Jai-Hwang;Kim, Hyun-Gyun
    • Transactions on Electrical and Electronic Materials
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    • v.13 no.1
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    • pp.16-18
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    • 2012
  • LED lighting systems that combine lighting capability, emotional and physiological characteristics are required for lighting source and multifunctional applications. In this work, Simulation studies using optical analysis software packages, Light Tools, are presented. This is done to estimate the uniformity ratio of illuminance and photosynthetic photon flux density (PPFD) of the periodic 2D lattice arrangements, such as square, diamond, two-way bias quadrangular, hexagonal, and Kagome lattices, under the same transmissivity, absorptance and reflectivity. It has been found out that the two-dimensional Kagome lattice arrangement exhibited high uniformity ratio of illuminance and PPFD compared to other lattices. Accordingly, these results can be used to guide a design and improve the lighting environment which in turn would maximize the uniform distributions of illuminance.

Development of Electronic Limit Switch for the Drive Unit of Incore Detector System Application (노내 핵계측 계통 구동기기의 전자식 한계스위치 개발)

  • 박종범;양승권;이상효
    • Journal of the Korean Institute of Illuminating and Electrical Installation Engineers
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    • v.14 no.4
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    • pp.1-7
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    • 2000
  • In this paper, we study a cause of malfunction of switch to control drive motor in DFMS(Digital Flux Mapping System) which can measure incore neutron flux of the nuclear plant, and develope a method to solve this problem. DFMS has the type of generating contact signal by mechanical switch lever, which is operated whenever thimble detector inserted or withdrawed through thimble Guide Tube. However the characteristics of the lever tend to be changed by mechanical degrade or bad environment and the lever finally generates errotic contact signal. Therefore we installed electric coil ass'yin the outside of Guide Tube instead of mechanical switch assy's. In addition we applied resonance effect to control circuit and installed condenser in the input of power supply to protect noise and interference. After completion of this improvement, we tested this improved device repetitively under the various conditions. In conclusion, we identified the generation of the desired contact signal and the prevention of detector failure through plant surveillance test during normal plant operation.

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Evaluation of Neutron Flux Distributions of SMART-P IST Region for the Design of Ex-Core Detector (SMART 연구로 노외계측기 설계를 위한 IST 영역의 중성자속 분포 평가)

  • Koo, Bon-Seung;Kim, Kyo-Youn;Lee, Chung-Chan;Zee, Sung-Quun
    • Journal of Radiation Protection and Research
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    • v.30 no.2
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    • pp.55-60
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    • 2005
  • The evaluation of neutron flux distribution was performed for the ex-core detector design of SMART-P. DORT and MCNP code were used for the calculation of energy-dependent neutron flux distribution at 100% full power condition. Two code results show that maximum thermal flux appears at the $1^{st}$ water region in IST region and agree within 10% difference. In addition, another evaluation was performed code with assumptions that cote was composed of fission source and control rod without fuel assemblies. These assumptions make neutron count rate to be minimized. As a results, maximum thermal flux showed $6.99{\times}10^{-2}(n/cm^2-sec)$, when the strength of initial fission source was assumed as $1.0{\times}10^8(n/sec)$. The main reason of these results is due to the thermalization of fast neutrons in the water region and thermal flux is proportional to 80% of total neutron flux. Therefore, optimization of filler material of detector guide tube, position of installation and axial length of detector segments is necessary for the design of ex-core detector to enhance the neutron count rate and above results could be used in ex-core detector design as a fluence requirement.

Study of Optical Design Method for Ultra Slim Backlight System Using LED Light Source (LED광원을 이용한 초박형 백라이트에 대한 광학설계기법의 연구)

  • Han, Jeong-Min;Han, Jin-Woo;Kim, Byoung-Young;Kim, Jong-Yeon;Kim, Young-Hwan;Kim, Jong-Hwan;Seo, Dae-Shik
    • Proceedings of the Korean Institute of Electrical and Electronic Material Engineers Conference
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    • 2007.11a
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    • pp.432-432
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    • 2007
  • We studied optical simulation method for ultra slim backlight system. We designed 0.7mm thickness light guide plate and combined 48 white color LEDs for 12 inch wide size TFT-LCD. We designed flat shape PMMA light guide plate with both side patterned. It have vertical prism shape on upper side and ellipse dot pattern on the other side. We targeted 4500 nit brightness and uniform emission characteristic without hot spot or dark area. At first, we designed uniform emission area with more high brightness in center area and then, debugged light entering hot spot zone and direction of outgoing light flux. Although it was designing step, we obtained good result with reverse prism optical sheet and it had good repeatability because it was based on the stamper method in injection process without laser engraving or micro groove engraving method.

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Neutron Flux Evaluation on the Reactor Pressure Vessel by Using Neural Network (인공신경 회로망을 이용한 압력용기 중성자 조사취화 평가)

  • Yoo, Choon-Sung;Park, Jong-Ho
    • Journal of Radiation Protection and Research
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    • v.32 no.4
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    • pp.168-177
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    • 2007
  • A neural network model to evaluate the neutron exposure on the reactor pressure vessel inner diameter was developed. By using the three dimensional synthesis method described in Regulatory Guide 1.190, a simple linear equation to calculate the neutron spectrum on the reactor pressure vessel was constructed. This model can be used in a quick estimation of fast neutron flux which is the most important parameter in the assessment of embrittlement of reactor pressure vessel. This model also used in the selection of an optimum core loading pattern without the neutron transport calculation. The maximum relative error of this model was less than 3.4% compared to the transport calculation for the calculations from cycle 1 to cycle 23 of Kori unit 1.

Optimized Magnetic Shielding for the MagLev Vechicles (자기부상열차의 최적 자기 차폐)

  • 윤현보;박찬일;박희창;손영수;임계재
    • The Proceeding of the Korean Institute of Electromagnetic Engineering and Science
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    • v.2 no.3
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    • pp.17-25
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    • 1991
  • Magnetic leakage flux which is generated from the levitation magnets, linear induction motors, and guide magnets of a MagLev(Magnetic Levitation) system is directly related to inter - system EMI, intra - system EMI, and biological effects. In this paper, the magnetic leakage flux from MagLev vechicles designed by Korea Resarch Institute of Ships & Ocean Engineering was calculated considering the various parameters which influence ma- gnetic field intensity around the MagLev system. Based on the calculated field intensity, the thickness of shielding material and shielding position for MagLev floor and side walls are calculated, taking into account the shielding effectiveness of a shield with minimum weight. For the nonuniform shielding method derived from the above procedure, the weight of a shield con- sisting of floor and side walls shielding can be reduced to more 50% than uniform shielding method.

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Verification of Quantitative Evaluation Method for Ferritic Weld Metal Microstructure (철강 용착금속 미세조직의 정량화 기법 검증)

  • Kim Ka-Hee;Kim Hee-Jin;Ryoo Hoi-Soo
    • Journal of Welding and Joining
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    • v.23 no.4
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    • pp.27-33
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    • 2005
  • Quantitative evaluation was performed on the microstructure of flux-cored arc(FCA) weld metal using a method blown as IIW scheme. It was mainly intended to figure out any practical difficulties in applying this method and also to provide the consumable makers with basic guide line in developing FCA welding consumables far better properties. Assessment of the experimental results showed IIW scheme was quite reliable in the low heat input range where the acicular ferrite was a major constituent. However, in the high heat input range, some scatter was noticed as the other phases like grain boundary ferrite and Widmansttaten ferrite become dominant. It implies that the accuracy of IIW scheme depends on the faction of microstructural constituents and it become worse as the fraction of latter two phases increases. This tendency was discussed in terms of the characteristics of those two phases. In addition, base line microstructure of rutile type FCA weld metal was addressed for developing new FCA welding consumables intended for higher heat input welding.