• Title/Summary/Keyword: Core Pin

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The Optimization of Chemical Treatments through the Six Sigma Innovation Activity (6시그마 혁신활동을 통한 약품처리 최적화)

  • Kim Tai Kyoo;Kim Hong Chul
    • Journal of Korea Technology Innovation Society
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    • v.7 no.3
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    • pp.641-656
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    • 2004
  • L Company is producing the second sept pin, Shadow Mask which is the chief part of CRT in W, Monitor. Inside of the CRT pan, Shadow Mask leads the electronic beam to express the three primary colors; red, green, blue, and it is the core part to embody the colors. In the etching process, it produces this part with manufacturing by eroding the iron chloride. Even though the iron chloride is harmless to human body. it is necessary to diminish the amount of it on the view of preservation of environment. In addition, by studying the method of the dispossed liquid process, cutting down the manufacturing cost is a necessary task on the aspect of reconsideration of competitive business. This study shows the case that through the six sigma innovation activity, it reforms the following the former processing flow, and it reduces the amount of it by improving the efficiency of the iron chloride. By rationalization of the standard requirement cooperative company, it could cut down the manufacturing cost in the cooperative company, so it could promote the common profits.

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Development of a fast reactor multigroup cross section generation code EXUS-F capable of direct processing of evaluated nuclear data files

  • Lim, Changhyun;Joo, Han Gyu;Yang, Won Sik
    • Nuclear Engineering and Technology
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    • v.50 no.3
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    • pp.340-355
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    • 2018
  • The methods and performance of a fast reactor multigroup cross section (XS) generation code EXUS-F are described that is capable of directly processing Evaluated Nuclear Data File format nuclear data files. RECONR of NJOY is used to generate pointwise XS data, and Doppler broadening is incorporated by the Gauss-Hermite quadrature method. The self-shielding effect is incorporated in the ultrafine group XSs in the resolved and unresolved resonance ranges. Functions to generate scattering transfer matrices and fission spectrum matrices are realized. The extended transport approximation is used in zero-dimensional calculations, whereas the collision probability method and the method of characteristics are used for one-dimensional cylindrical geometry and two-dimensional hexagonal geometry problems, respectively. Verification calculations are performed first for various homogeneous mixtures and cylindrical problems. It is confirmed that the spectrum calculations and the corresponding multigroup XS generations are performed adequately in that the reactivity errors are less than 50 pcm with the McCARD Monte Carlo solutions. The nTRACER core calculations are performed with the EXUS-F-generated 47 group XSs for the two-dimensional Advanced Burner Reactor 1000 benchmark problem. The reactivity error of 160 pcm and the root mean square error of the pin powers of 0.7% indicate that EXUF-F generates properly the broad-group XSs.

TEM investigation of helium bubble evolution in tungsten and ZrC-strengthened tungsten at 800 and 1000℃ under 40keV He+ irradiation

  • I. Ipatova;G. Greaves;D. Terentyev;M.R. Gilbert;Y.-L. Chiu
    • Nuclear Engineering and Technology
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    • v.56 no.4
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    • pp.1490-1500
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    • 2024
  • Helium-induced defect nucleation and accumulation in polycrystalline W and W0.5 wt%ZrC (W0.5ZrC) were studied in-situ using the transmission electron microscopy (TEM) combined with 40 keV He+ irradiation at 800 and 1000℃ at the maximum damage level of 1 dpa. Radiation-induced dislocation loops were not observed in the current study. W0.5ZrC was found to be less susceptible to irradiation damage in terms of helium bubble formation and growth, especially at lower temperature (800 ℃) when vacancies were less mobile. The ZrC particles present in the W matrix pin the forming helium bubbles via interaction between C atom and neighbouring W atom at vacancies. This reduces the capability of helium to trap a vacancy which is required to form the bubble core and, as a consequence, delays, the bubble nucleation. At 1000 ℃, significant bubble growth occurred in both materials and all the present bubbles transitioned from spherical to faceted shape, whereas at 800 ℃, the faceted helium bubble population was dominated in W.

Improvement of crossflow model of MULTID component in MARS-KS with inter-channel mixing model for enhancing analysis performance in rod bundle

  • Yunseok Lee;Taewan Kim
    • Nuclear Engineering and Technology
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    • v.55 no.12
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    • pp.4357-4366
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    • 2023
  • MARS-KS, a domestic regulatory confirmatory code of Republic of Korea, had been developed by integrating RELAP5/MOD2 and COBRA-TF. The integration of COBRA-TF allowed to extend the capability of MARS-KS, limited to one-dimensional analysis, to multi-dimensional analysis. The use of COBRA-TF was mainly focused on subchannel analyses for simulating multi-dimensional behavior within the reactor core. However, this feature has been remained as a legacy without ongoing maintenance. Meanwhile, MARS-KS also includes its own multidimensional component, namely MULTID, which is also feasible to simulate three-dimensional convection and diffusion. The MULTID is capable of modeling the turbulent diffusion using simple mixing length model. The implementation of the turbulent mixing is of importance for analyzing the reactor core where a disturbing cross-sectional structure of rod bundle makes the flow perturbation and corresponding mixing stronger. In addition, the presence of this turbulent behavior allows the secondary transports with net mass exchange between subchannels. However, a series of assessments performed in previous studies revealed that the turbulence model of the MULTID could not simulate the aforementioned effective mixing occurred in the subchannel-scale problems. This is obvious consequence since the physical models of the MULTID neglect the effect of mass transport and thereby, it cannot model the void drift effect and resulting phasic distribution within a bundle. Thus, in this study, the turbulence mixing model of the MULTID has been improved by means of the inter-channel mixing model, widely utilized in subchannel analysis, in order to extend the application of the MULTID to small-scale problems. A series of assessments has been performed against rod bundle experiments, namely GE 3X3 and PSBT, to evaluate the performance of the introduced mixing model. The assessment results revealed that the application of the inter-channel mixing model allowed to enhance the prediction of the MULTID in subchannel scale problems. In addition, it was indicated that the code could not predict appropriate phasic distribution in the rod bundle without the model. Considering that the proper prediction of the phasic distribution is important when considering pin-based and/or assembly-based expressions of the reactor core, the results of this study clearly indicate that the inter-channel mixing model is required for analyzing the rod bundle, appropriately.

A Study on the Fiber-Optic Voltage Sensor Using EMO-BSO (EOM-BSO 소자를 이용한 광전압센서에 관한 연구)

  • Kim, Yo-Hee;Lee, Dai-Young
    • Journal of the Korean Institute of Telematics and Electronics
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    • v.27 no.11
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    • pp.119-125
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    • 1990
  • This paper describes fiber optic voltage sensor using EOM-BSO (Electro-Optic Modulator-Bismuth Silicon Oxcide). Transceiver has an electical/optical converter and an optical/electrical converter which consist of light emitting diode, PIN-PD, and electronic circuits. Multimode fiber cable of $100/140{\mu}m$ core/clad diameter is used for connecting the transceiver to fiber cable and fiber optic voltage sensor. Before our experiments, by applying the Maxwell equations and wave equations, We derive matrix equation on wave propagation in the BSO single crystal. And also we derive optimal equation on intensity modulation arising through an analyzer. According to experi-mental results, fiber optic voltage sensor has maximum $2.5{\%}$ error within the applied AC voltage of 800V. As the applied voltage increases, saturation values of voltage sensor also increase. This phenomenon is caused by optical rotatory power of BSO single crystal. And temperature dependence of sensitivity for fiber optical rotatory power of BSO single crystal. And temperature dependence of sensitivity for fiber optic voltage sensor in the temperature range from$-20^{\circ}C\to\60^{\circ}C$ are measured within ${\pm}0.6{\%}$. And frequency characteristics of the voltage sensor has good frequency characteristics from DC to 100kHz.

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Implementation of User Interface for DNA Micro Array Printing Technology (DNA 마이크로어레이 프린팅을 위한 사용자 인터페이스 적용기술)

  • Park, Jae-Sam
    • The Journal of the Korea institute of electronic communication sciences
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    • v.8 no.12
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    • pp.1875-1882
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    • 2013
  • Micro-array technology contributes numerous achievements such as ordering of gene network and integration of genomic. This technology is well established as means for investigating patterns of gene expression. DNA micro-arrays utilize Affymetric chips where a large quantity of DNA sequences may be synthesized. There are two general type of conventional DNA array spotter: contact and piezoelectric. The contact technology used spotting pin technology to make contact with the glass slide surface. This may caused damage or scratches to the surface matrix where protein will be contaminated and may not bind specifically. Piezoelectric technology available at this present time on the other hand requires the analyzer to print the result that can only be done within the laboratory despite of mass production. Therefore, in this paper, high-throughput technology is developed for providing greater consistency in feature spot without touching the glass slide surface.

An experimental study of the behaviour of double sided welded plate connections in precast concrete frames

  • Gorgun, Halil
    • Steel and Composite Structures
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    • v.29 no.1
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    • pp.1-22
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    • 2018
  • Multi-storey precast concrete skeletal structures are assembled from individual prefabricated components which are erected on-site using various types of connections. In the current design of these structures, beam-to-column connections are assumed to be pin jointed. Welded plate beam to-column connections have been used in the precast concrete industry for many years. They have many advantages over other jointing methods in component production, quality control, transportation and assembly. However, there is at present limited information concerning their detailed structural behaviour under bending and shear loadings. The experimental work has involved the determination of moment-rotation relationships for semi-rigid precast concrete connections in full scale connection tests. The study reported in this paper was undertaken to clarify the behaviour of such connections under symmetrical vertical loadings. A series of full-scale tests was performed on sample column for which the column geometry and weld arrangements conformed with successful commercial practice. Proprietary hollow core slabs were tied to the beams by tensile reinforcing bars, which also provide the in-plane continuity across the connections. The strength of the connections in the double sided tests was at least 0.84 times the predicted moment of resistance of the composite beam and slab. The secant stiffness of the connections ranged from 0.7 to 3.9 times the flexural stiffness of the attached beam. When the connections were tested without the floor slabs and tie steel, the reduced strength and stiffness were approximately a third and half respectively. This remarkable contribution of the floor strength and stiffness to the flexural capacity of the joint is currently neglected in the design process for precast concrete frames. In general, the double sided connections were found to be more suited to a semi-rigid design approach than the single sided ones. The behaviour of double sided welded plate connection test results are presented in this paper. The behaviour of single sided welded plate connection test results is the subject of another paper.

Design and Implementation of an InfiniBand System Interconnect for High-Performance Cluster Systems (고성능 클러스터 시스템을 위한 인피니밴드 시스템 연결망의 설계 및 구현)

  • Mo, Sang-Man;Park, Kyung;Kim, Sung-Nam;Kim, Myung-Jun;Im, Ki-Wook
    • The KIPS Transactions:PartA
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    • v.10A no.4
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    • pp.389-396
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    • 2003
  • InfiniBand technology is being accepted as the future system interconnect to serve as the high-end enterprise fabric for cluster computing. This paper presents the design and implementation of the InfiniBand system interconnect, focusing on an InfiniBand host channel adapter (HCA) based on dual ARM9 processor cores The HCA is an SoC tailed KinCA which connects a host node onto the InfiniBand network both in hardware and in software. Since the ARM9 processor core does not provide necessary features for multiprocessor configuration, novel inter-processor communication and interrupt mechanisms between the two processors were designed and embedded within the KinCA chip. Kinch was fabricated as a 564-pin enhanced BGA (Bail Grid Array) device using 0.18${\mu}{\textrm}{m}$ CMOS technology Mounted on host nodes, it provides 10 Gbps outbound and inbound channels for transmit and receive, respectively, resulting in a high-performance cluster system.

Long-term structural analysis and stability assessment of three-pinned CFST arches accounting for geometric nonlinearity

  • Luo, Kai;Pi, Yong-Lin;Gao, Wei;Bradford, Mark A.
    • Steel and Composite Structures
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    • v.20 no.2
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    • pp.379-397
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    • 2016
  • Due to creep and shrinkage of the concrete core, concrete-filled steel tubular (CFST) arches continue to deform in the long-term under sustained loads. This paper presents analytical investigations of the effects of geometric nonlinearity on the long-term in-plane structural performance and stability of three-pinned CFST circular arches under a sustained uniform radial load. Non-linear long-term analysis is conducted and compared with its linear counterpart. It is found that the linear analysis predicts long-term increases of deformations of the CFST arches, but does not predict any long-term changes of the internal actions. However, non-linear analysis predicts not only more significant long-term increases of deformations, but also significant long-term increases of internal actions under the same sustained load. As a result, a three-pinned CFST arch satisfying the serviceability limit state predicted by the linear analysis may violate the serviceability requirement when its geometric nonlinearity is considered. It is also shown that the geometric nonlinearity greatly reduces the long-term in-plane stability of three-pinned CFST arches under the sustained load. A three-pinned CFST arch satisfying the stability limit state predicted by linear analysis in the long-term may lose its stability because of its geometric nonlinearity. Hence, non-linear analysis is needed for correctly predicting the long-term structural behaviour and stability of three-pinned CFST arches under the sustained load. The non-linear long-term behaviour and stability of three-pinned CFST arches are compared with those of two-pinned counterparts. The linear and non-linear analyses for the long-term behaviour and stability are validated by the finite element method.

Validation of spent nuclear fuel decay heat calculation by a two-step method

  • Jang, Jaerim;Ebiwonjumi, Bamidele;Kim, Wonkyeong;Park, Jinsu;Choe, Jiwon;Lee, Deokjung
    • Nuclear Engineering and Technology
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    • v.53 no.1
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    • pp.44-60
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    • 2021
  • In this paper, we validate the decay heat calculation capability via a two-step method to analyze spent nuclear fuel (SNF) discharged from pressurized water reactors (PWRs). The calculation method is implemented with a lattice code STREAM and a nodal diffusion code RAST-K. One of the features of this method is the direct consideration of three-dimensional (3D) core simulation conditions with the advantage of a short simulation time. Other features include the prediction of the isotope inventory by Lagrange non-linear interpolation and the use of power history correction factors. The validation is performed with 58 decay heat measurements of 48 fuel assemblies (FAs) discharged from five PWRs operated in Sweden and the United States. These realistic benchmarks cover the discharge burnup range up to 51 GWd/MTU, 23.2 years of cooling time, and spanning an initial uranium enrichment range of 2.100-4.005 wt percent. The SNF analysis capability of STREAM is also employed in the code-to-code comparison. Compared to the measurements, the validation results of the FA calculation with RAST-K are within ±4%, and the pin-wise results are within ±4.3%. This paper successfully demonstrates that the developed decay heat calculation method can perform SNF back-end cycle analyses.