• Title/Summary/Keyword: Rod

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Light microscopic evidence of in vivo differentiation from the transplanted inferior turbinate-derived stem cell into the rod photoreceptor in degenerating retina of the mouse

  • Yong Soo Park;Yeonji Kim;Sung Won Kim; In-Beom Kim
    • Applied Microscopy
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    • v.50
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    • pp.11.1-11.3
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    • 2020
  • The human turbinate-derived mesenchymal stem cells (hTMSCs), which were DiI-labeled and transplanted into the subretinal space in degenerating mouse retina, were observed in retinal vertical sections processed for rhodopsin (a marker for rod photoreceptor) by confocal microscope with differential interference contrast (DIC) filters. The images clearly demonstrated that DiI-labeled hTMSCs have rhodopsin-immunoreactive appendages, indicating differentiation of transplanted hTMSC into rod photoreceptor. Conclusively, the finding suggests therapeutic potential of hTMSCs in retinal degeneration.

The Development of Balanced Scorecards Model based on the Strategic Plan of the Rod Library, UNI (전략적 계획을 기반으로 한 BSC 모형 개발 -Rod Library 사례를 중심으로-)

  • Cho, Yoon-Hee
    • Journal of the Korean Society for information Management
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    • v.23 no.1 s.59
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    • pp.159-179
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    • 2006
  • The University of Northern iowa Rod Library has mission statement that a personalized learning environment founded on the strong liberal arts curriculum and to supporting an intellectually and culturally diverse community. The Rod Library has been developing the strategic plans by 5 years since 1987 Recently, the strategy has been faced need to measure of performance how much does make it up. This study developed the BSC model and the strategy map that analyze the strategic plan 2004-2009 of the University of Northern iowa Rod library and transfer the strategy into the four perspectives of BSC. In addition, this study presented the success performance indicators measuring the strategic goals of each perspectives and the cause-effect model driving the lead indicators of performance.

Comparative Analysis on Ground Impedance for a Carbon Block and a Copper Rod (탄소블록과 동봉의 접지임피던스 비교 분석)

  • Seo, Jae-Suk;Park, Hee-Chul;Kil, Gyung-Suk;Oh, Jae-Geun
    • Journal of the Korean Institute of Electrical and Electronic Material Engineers
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    • v.26 no.6
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    • pp.472-477
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    • 2013
  • This paper carried out the comparative analysis on ground impedance of a carbon block and a copper rod. Two types of grounding electrode were compared ; a carbon block (L : 1 m, ${\Phi}$ : 245 mm) buried at a depth of 0.8 m and a three-linked copper rod (L : 1 m, ${\Phi}$ : 10 mm) of equilateral triangles with 1 m spacing. Ground impedance depending on applied current source was evaluated by the application of a sine wave current with 60 Hz ~ 3.5 MHz, a fast-rise pulse with rising time of 200 ns, a standard lightning impulse of $8/20{\mu}s$ and a 600 Hz square wave. Ground impedance for both electrodes were almost the same value below 100 kHz, and increased rapidly afterwards. The maximum ground impedance appeared $400{\Omega}$ at around 1.5 MHz. Ground impedance of the carbon block was lower at the square wave and was higher at fast-rise pulse than that of the copper rod. Also, ground impedance as ages showed no difference for the last 8 months. From the results, it is likely that ground performance for both electrodes shows no difference against commercial frequency and lightning impulse current, while the copper rod shows better performance against a fast-rise pulse with rise-time of a few hundred ns.

High Precision Solenoid Type Nuclear Reactor Control Rod Position Indicator (고정밀도 솔레노이드 방식의 원자로 제어봉 위치지시기)

  • Baek, Min-Ho;Hong, Hoon-Bin;Park, Hee-June
    • The Transactions of The Korean Institute of Electrical Engineers
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    • v.65 no.11
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    • pp.1848-1853
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    • 2016
  • Control Rod Position Indicator in nuclear reactor vessel has developed for small reactor in Korea. Because of severe environment in reactor vessel, target of this study is to develop the suitable position indicator. In this study, solenoid type position indicator made of Mineral Insulated Cable(MI Cable) was introduced to adapt in severe environment. And inductance of the solenoid was used to indicate the rod position for high precision. But problem of this concept is that a linear slope of inductance is changed by temperature effect. To resolve this problem, two sensing coils were introduced for temperature compensation. A role of the sensing coil is to make reference linear equation about certain temperature. To confirm this concept, also, inductance of solenoid and sensing coils were measured at room and high temperature (${\sim}300^{\circ}C$). The results of measurement show that the position error of sensing coil between room and high temperature was about 2%. But it was identified that this error was resulted from insufficient test environment (temperature error between solenoid and sensing coils was about 2% at high temperature condition). Therefore, solenoid type position indicator shows that it is very suitable in reactor vessel as a high precision rod position indicator.

The Defect Inspection on the Irradiated Fuel Rod by Eddy Current Test (와전류시험에 의한 조사핵연료봉의 결함 검사)

  • Koo, D.S.;Park, Y.K.;Kim, E.K.
    • Journal of the Korean Society for Nondestructive Testing
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    • v.16 no.1
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    • pp.29-33
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    • 1996
  • The eddy current test(ECT) probe of differential encircling coil type was designed and fabricated, and the optimum condition of ECT was derived for the examination of the irradiated fuel rod. The correlation between ECT test frequency and phase & amplitude was derived by performing the test of the standard rig that includes inner notches, outer notches and through-holes. The defect of through-hole was predicted by ECT at the G33-N2 fuel rod irradiated in the Kori-1 nuclear power reactor. The metallographic examination on the G33-N2 fuel rod was Performed at the defect location predicted by ECT. The result of metallographic examination for the G33-N2 fuel rod was in good agreement with that of ECT. This proves that the evaluation for integrity of irradiated fuel rod by ECT is reliable.

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Vibration Characteristic Analysis of an Annular Cylindrical PWR Fuel Rod according to the Cross-sectional Dimensions and the Span Length (가압경수로용 환형 실린더 연료봉의 단면치수와 스팬길이에 따른 진동특성해석)

  • Lee, Kang-Hee;Kim, Jae-Yong;Lee, Yung-Ho;Yoon, Kyung-Ho;Kim, Hyung-Kyu
    • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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    • 2007.05a
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    • pp.197-201
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    • 2007
  • Vibration characteristics of an annular cylindrical fuel rod, which was proposed as a candidate design of fuel's cross section for the ultra-high burnup nuclear fuel, according to the cross-sectional dimensions and the number of supports or the span length were analytically studied. Finite element(FE) modeling for the annular cross sectional fuel was based on the methodology, that have been proven by the test verification, for the conventional PWR nuclear fuel rod. A commercial FEA code, ABAQUS, was used for the FE modeling and analysis. A planar beam element (B21) that uses a linear interpolation was used for the fuel rod and a linear spring element for the spring and dimple of the SG. Natural frequencies and mode shape were calculated according to the preliminary design candidates for the fuel's cross sectional dimension and the number of span. From the analysis results, the design scheme of the annular fuel compatible to the present PWR nuclear reactor core was discussed in terms of the number of supports and fuel's cross section.

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Measurements of Turbulent Flow In a$6\times{6}$ Rod Bundle with Spacer Grids (지지격자를 갖는 $6\times{6}$ 봉다발에서의 난류유동 측정)

  • Yang, Sun-Kyu;Chung, Moon-Ki
    • Nuclear Engineering and Technology
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    • v.28 no.2
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    • pp.162-174
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    • 1996
  • The local hydraulic characteristics in a single phase flow of a 6$\times$6 rod bundle with neighboring different spacer grids were measured by using a LDV(Laser Doppler Velocimeter) system. 6$\times$6 rod bundle is formed by two 3$\times$6 rod bundles with different spacer grids. The objective of this study in a rod bundle is to investigate the thermal-hydraulic interactions between different spacer grids with different configurations and resistance. By using a LDV system, the velocity and turbulent intensity in axial and horizontal directions ore measured. Pressure drop measurements ore also performed to evaluate the loss coefficient for the spacer grid and the friction factor for rod bundles. Implications concerning thermal mining due to spacer grids were investigated based on the hydraulic test results. Swirl factor, which is assumed as a qualitative criteria for DNB(departure from nucleate boiling), was defined and estimated from the horizontal velocity result.

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Free Vibration Characteristics of 5 × 5 Spacer Grid Assembly Supporting the PWR Fuel Rod (경수로 연료봉을 지지하는 5×5 지지격자체의 자유진동특성)

  • 강흥석;윤경호;송기남;최명환
    • Transactions of the Korean Society for Noise and Vibration Engineering
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    • v.14 no.6
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    • pp.512-519
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    • 2004
  • This paper described the free vibration characteristics of Optimized H Type (OHT) spacer grids (SG) supporting the PWR fuel rod. The vibration test and the finite element (FE) analysis are performed under the free boundary condition and the clamped at two points (or three points) in the bottom which is the same one as the experimental condition for the dummy rod continuously supported by spacer grids. A modal test is conducted by the impulse excitation method using an impulse hammer and an accelerometer, and the TDAS module of the I-DEAS software is used to acquire and analyze the sensor signals. The softwares related to the FE analysis are the I-DEAS for the geometrical shape modeling and meshing, and the ABAQUS for solving. The fundamental frequency of the OHT SG by experiment under a clamped condition at two points is 175.18 Hz, and shows a bending mode. We think there is no resonance between the fuel rod and the SG because the SG's frequency is higher than that of the fuel rod existing in the range from 30 to 120 Hz. The fundamental frequency of the SG under the free boundary condition is 349.2 Hz showing a bending mode, and the results between the test and the analysis have a good agreement with maximum 7 % in error It is also found that the FE analysis model of the OHT SGs to analyze an impact, a buckling and vibration et al. has been generated with reliability.