• 한국염색가공학회지
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• 제22권2호
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• pp.140-144
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• 2010

In this study, we investigated the clean appearance and good stretch properties. Usually, clean appearance concerned with the dyeing properties of core and effect yarns. The dyeing properties between core yarn (conjugate yarn) and effect yarn were determined by the build-up and the color differences using the four different yarns of SDY FD(spindraw yarn full dull), SDY CD(spindraw yarn cation dyeable), POY FD( partially-oriented yarn full dull) and POY CD(partially-oriented yarn cation dyeable). We used the single color dye of C. I. Disperse Blue 79 and mixed colors made by C. I. Disperse Red 60, C. I. Disperse Blue 56, and C. I. Disperse Yellow 54.

• 한국잠사학회:학술대회논문집
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• 한국잠사학회 2001년도 제44회 추계 학술연구 발표회
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• pp.39-39
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• 2001

no Abstract, See Full Text

• Nuclear Engineering and Technology
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• 제52권5호
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• pp.878-888
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• 2020

This paper presents the validation of UNIST in-house Monte Carlo code MCS used for the high-fidelity simulation of commercial pressurized water reactors (PWRs). Its focus is on the accurate, spatially detailed neutronic analyses of startup physics tests for the initial core of the Watts Bar Nuclear 1 reactor, which is a vital step in evaluating core phenomena in an operating nuclear power reactor. The MCS solutions for the Consortium for Advanced Simulation of Light Water Reactors (CASL) Virtual Environment for Reactor Applications (VERA) core physics benchmark progression problems 1 to 5 were verified with KENO-VI and Serpent 2 solutions for geometries ranging from a single-pin cell to a full core. MCS was also validated by comparing with results of reactor zero-power physics tests in a full-core simulation. MCS exhibits an excellent consistency against the measured data with a bias of ±3 pcm at the initial criticality whole-core problem. Furthermore, MCS solutions for rod worth are consistent with measured data, and reasonable agreement is obtained for the isothermal temperature coefficient and soluble boron worth. This favorable comparison with measured parameters exhibited by MCS continues to broaden its validation basis. These results provide confidence in MCS's capability in high-fidelity calculations for practical PWR cores.

• Nuclear Engineering and Technology
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• 제56권3호
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• pp.933-940
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• 2024

A macroscopic cross section generation model was developed for the conceptual horizontal, compact high temperature gas reactor (HC-HTGR). Because there are many sources of spectral effects in the design and analysis of the core, conventional LWR methods have limitations for accurate simulation of the HC-HTGR using a neutron diffusion core neutronics simulator. Several super-cell model configurations were investigated to consider the spectral effect of neighboring cells. A new history variable was introduced for the existing library format to more accurately account for the history effect from neighboring nodes and reactivity control drums. The macroscopic cross section library was validated through comparison with cross sections generated using full core Monte Carlo models and single cell cross section for both 3D core steady-state problems and 2D and 3D depletion problems. Core calculations were then performed with the AGREE HTR neutronics and thermal-fluid core simulator using super-cell cross sections. With the new history variable, the super-cell cross sections were in good agreement with the full core cross sections even for problems with significant spectrum change during fuel shuffling and depletion.

• 전력전자학회:학술대회논문집
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• 전력전자학회 2008년도 하계학술대회 논문집
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• pp.379-381
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• 2008

Generally additional leakage inductance and two clamp diodes are adopted into the conventional phase shift full bridge (PSFB) converter for reducing the voltage stress of secondary rectifier diodes and extending the range of zero voltage switching (ZVS) operation. However, since additional leakage inductance carries the ac current similar to the primary one, the core and copper loss oriented from additional leakage inductance can be high enough to decrease the whole efficiency of DC/DC converter. Therefore, in this paper, a new ZVS phase shift full bridge converter with separated primary winding (SPW) is proposed. Proposed converter makes the transformer and additional leakage inductor with one ferrite core. Using this method, leakage inductance is controlled by the winding ratio of separated primary winding. Moreover, by manufacturing the both magnetic components with one core, size and core loss can be reduced and it turns out the improvement of efficiency and power density of DC/DC converter. The operational principle of proposed converter is analyzed and verified by the 1.2kW prototype.

• Nuclear Engineering and Technology
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• 제56권3호
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• pp.980-992
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• 2024

Steam line break accident (SLB) in the nuclear reactor is one of the representative Non-LOCA accidents in which thermal-hydraulics and neutron kinetics are strongly coupled each other. Thus, the multi-scale and multi-physics approach is applied in this study in order to examine a realistic safety margin. An entire reactor coolant system is modelled by system scale node, whereas sub-channel scale resolution is applied for the region of interest such as the reactor core. Fuel performance code is extended to consider full core pin-wise fuel behaviour. The MARU platform is developed for easy integration of the codes to be coupled. An initial stage of the steam line break accident is simulated on the MARU platform. As cold coolant is injected from the cold leg into the reactor pressure vessel, the power increases due to the moderator feedback. Three-dimensional coolant and fuel behaviour are qualitatively visualized for easy comprehension. Moreover, quantitative investigation is added by focusing on the enhancement of safety margin by means of comparing the minimum departure from nucleate boiling ratio (MDNBR). Three factors contributing to the increase of the MDNBR are proposed: Various geometric parameters, realistic power distribution by neutron kinetics code, Radial coolant mixing including sub-channel physics model.

• 한국음향학회:학술대회논문집
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• 한국음향학회 2001년도 추계학술발표대회 논문집 제20권 2호
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• pp.9-12
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• 2001

본 논문에서는 유럽 통신 표준화기구인 ETSI 의 SMGll에서 채택된 GSM Full Rate(FR) 보코더 알고리wma[1]을 Teak DSP Core를 이용하여 실시간 구현하였다. GSM FR 보코더는 유럽에서 사용하는 통신 시스템인 GSM 의 full-rate Traffic Channel(TCH)의 표준 코덱[2]으로서 GSM HR, GSM EFR GSM AMR과 더불어 모뎀칩 내에 장착되는 필수적인 음성 서비스이다. 구현된 GSM FR는 13.05kbps의 비트율을 가지고 있으며, 인코더와 디코더 기능 외에 voice activity detection(VAD)[3]블록과 DTX[4]블록 등의 부가 기능도 구현되어 있다. 구현에 사용된 Teak[5]는 DSP Group 의 16bit고정 소수점 DSP core로서 최대 140MIPS 의 성능을 낼 수 있고 400bits ALU 와 두개의 MAC 이 장착되어 있어 음성 및 채널 부호화기의 실시간 처리에 최적화 되어있다. 구현된 GSM FR 은 인코더와 디코더 부분이 각각 약 235 MIPS 및 1.19MIPS 의 복잡도를 나타내며, 사용된 메모리는 프로그램 ROM 3.9K words, 데이터 ROM(table) 396 words 및 RAM 932words이다.

• Nuclear Engineering and Technology
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• 제54권10호
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• pp.3724-3731
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• 2022

It is important for an ICRF full wave code to simulate the SOL (Scrape Off Layer) plasma as well as the core inside of the LCFS (Last Closed Flux Surface) for the precise prediction of the coupling between the antenna and the core plasma in tokamaks. To this end, a two dimensional full wave code based on a Fourier spectral algorithm has been developed. The spectral algorithm and procedures are described and the simulation results for the minority heating in KSTAR are reported including electric field, power absorption and power flux.

• 벤처혁신연구
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• 제5권1호
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• pp.129-143
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• 2022

본 연구의 목적은 자기연민과 삶의 만족의 관계에서 사회에 대한 인식과 자신에 대한 평가의 매개효과를 보는 것이다. 이를 위해 자기연민척도와 삶의 만족도 척도를 사회적 안녕감과 핵심자기평가와 함께 직장인 215명에게 실시하였다. 연구결과, 사회적 안녕감과 핵심자기평가는 자기연민과 삶의 만족도 간의 관계를 완전 매개 하였고, 사회적 안녕감과 핵심자기평가의 간접효과 간의 차이는 유의하지 않았다. 이러한 결과는 자기연민이 삶의 만족도를 개선하는 효과가 사회적 안녕감과 핵심자기평가를 통해 설명될 수 있음을 보여준다. 추후 연구를 위한 본 연구의 시사점과 제한점에 대해 논의하였다.

• Nuclear Engineering and Technology
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• 제29권5호
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• pp.375-384
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• 1997

Relative power density distributions of the Kori Unit 1 pressurized water reactor are calculated by Monte Carlo modeling with the MCNP code. The Kori Unit 1 core is modeled on a three-dimensional representation of the one-eighth of the reactor in-vessel component with reflective boundaries at 0 and 45 degrees. The axial core model is based on half core symmetry and is divided into four axial segments. Fission reaction density in each rod is calculated by following 100 cycles with 5,000 test neutrons in each cycle after starling with a localized neutron source and ten noncontributing settle cycles. Relative assembly power distributions are calculated from fission reaction densities of rods in assembly. After 100 cycle calculations, the system converges to a k value of 1.00039 $\geq$ 0.00084. Relative assembly power distribution is nearly the same with that of the Kori Unit 1 FSAR. Applicability of the full-scope Monte Carlo simulation in the power distribution calculation is examined by the relative root moan square error of 2.159%.