• Proceedings of the KWS Conference
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• 2005.06a
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• pp.241-243
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• 2005

• Proceedings of the Korean Nuclear Society Conference
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• 1999.10a
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• pp.105.2-105
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• 1999

• Proceedings of the Korean Society for Bio-Environment Control Conference
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• 1998.10a
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• pp.5-10
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• 1998

최근 온실에 온수 보일러를 설치하여 실내를 가온하는 시스템이 많이 도입되고 있다. 이들 장치들은 설정된 실내온도를 맞추기 위한 온도 제어장치가 부가되어 있지만, 대부분 ON-OFF제어 시스템을 구성하고 있기 때문에 온도 진폭의 현상이 발생하여 온도 제어 정밀성이 떨어지고 에너지소비도 많다. 이 문제점을 해결하기 위하여는 보일러 온수저장조와 온설 내 방열관 사이에 삼방변을 설치하고 설정온도, 실내온도 및 외기온을 비교하여 삼방변의 위치를 조절하여야 한다. (중략)

• Proceedings of the Korean Nuclear Society Conference
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• 1997.10a
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• pp.79-84
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• 1997

동특성 분석 코드 시스템 PANBOX2는 시간에 대한 미분을 Implicit Euler 방법을 사용하여 근사한다. 이 경우 Local Truncation Error는 중성자속의 이차 미분에 비례한다. Time-Step-Doubling 기법을 이용하여 Local Truncation Error의 근사치를 구하고 이를 이용하여 Time Step Size를 조절해 주는 방법을 동특성 분석 코드 시스템 PANBOX2에 도입하였다. LRA와 NEACRP 제어봉 인출사고 검증문제에 대한 분석 결과, PANBOX2 시스템의 기존 방법에 비해 효과적으로 Time Step을 제어하였으며 보다 정확한 결과를 얻을 수 있었다.

• Nuclear Engineering and Technology
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• v.26 no.2
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• pp.197-204
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• 1994

In a PWR rod cluster control assembly(RCCA) for shutdown is released upon action of control rod drive mechanism and falls down through the guide thimble by its weight. Drop time and impact velocity of the RCCA are two key parameters with respect to reactivity insertion time and the mechanical integrity of fuel assembly. Therefore, the precise control of drop time and impact velocity is prerequisite to modifying the existing design features of the RCCA and guide thimble or newly designing them. During its falling down into the core, the RCCA is retarded by various forces acting on it such as fluid resistance caused by the RCCA movement, buoyance and mechanical friction caused by contacting inner surface of the guide thimble, etc. However, complicated coupling of the various forces makes it difficult to derive an analytical dynamic equation for the drop time and impact velocity. This paper deals with the development of a computer program containing an analytical dynamic equation applicable to the Korean Fuel Assembly(KOFA). The computer program is benchmarked with an available single control rod drop tests. Since the predicted values are in good agreement with the test results, the computer program developed in this paper can be employed to modify the exiting design features of the RCCA and guide thimble and to develope their new design features for advanced nuclear reactors.

• Journal of the Korean Crystal Growth and Crystal Technology
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• v.8 no.1
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• pp.18-28
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• 1998

A laboratory experiment was made of a control of temperature oscillation in Czochralski convection. Numerical computation was also made to delineate the control of temperature oscillation. The suppression of temperature oscillation was achieved by varying the rotation rate of crystal rod ($\Omega=\Omega_0(1+A sin 2{\pi}ft/t_p)$), where A denotes the amplitude of rotation rate and f the frequency factor. Based on the inherent dimesionless time period of temperature oscillation ($t_p$), the suppression rate of temperature oscillation was characterized by the mixed convection parameter ($0.217{\leq}Ra/PrRe^2{\leq}1.658$). The optimal values of A and f were also scrutinized. To understand the suppression mechanism of temperature oscillation, the controls of isotherm($\theta$) and equi-vorticity($\omega$) were investigated.

• Computational Structural Engineering
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• v.10 no.3
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• pp.225-231
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• 1997

The dynamic characteristics of Control Element Drive Mechanism(CEDM) for Korea Standard Nuclear Power Plant are studied with the CEDM modeled as a secondary mass in a simplified two degree of freedom system, while the reactor vessel as a primary mass. The optimal .mu.-f curve is developed to reduce the response amplitudes of both primary and secondary masses. In order to improve a design it is proposed that the natural frequency ratio, f, should be converged to 0.93, the mass ratio, .mu., should not be reduced, and the result should be converged to the optimal .mu.-f curve. Optimal design for CEDM components has been carried out and the response amplitude ratios of reactor are reduced 10.5 - 19.7% while those of CEDM are reduced 6.3 - 3.4%.

• Nuclear Engineering and Technology
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• v.22 no.4
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• pp.371-379
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• 1990

The Xenon spatial oscillation may give rise to operational difficulties in a nuclear power plant. In this study, in order to investigate the Xenon instability for a PWR, the frequency-domain technique is adopted by using Generalized Nyquist Criterion, which is more general and suitable for the multi-input/multi-output system. Also linearized modal fluxes are obtained by a modal expansion. This model has been implemented to test the axial Xenon stability of YGN-1 unit against the changes in plant operating parameters ; power level, control rod position, and core average burnup. The results show that the increase of power level and the deeper insertion of control rod have the destabilizing effect, and that the burnup progress makes the core less stable. Also the results show that the overestimation due to modal interaction was found not to be significant.

• Proceedings of the KIEE Conference
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• 2009.07a
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• pp.2138.1_2139.1
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• 2009

COS 조작봉은 선로의 사고나 설비교체 또는 수리 등이 필요할 때 활선상태에서 COS를 개폐하기 위한 장비로서 보통 절연특성 및 강도가 우수하고 경량소재인 FRP(Fiberglass Reinforced Plastics)로 제작된다. 따라서 특고압 선로에서 작업 중 안전사고를 예방하기 위해 사용되는 장비인 만큼 안전거리 확보와 작업의 편리성을 고려하여 직접 조작봉을 연장하여 사용할 수 있도록 다단으로 제작되며, 조작봉의 크기는 작업조건에 따라 길이를 선택하여 사용할 수 있도록 2, 4, 6m급 등 길이에 따른 종류별로 생산되고 있다. 이러한 COS 조작봉의 사용특징은 장소와 시간에 관계없이 사용이 가능해야 하고, 특정한 사정에 의해선 작업자 혼자서 사용할 수 있도록 조작봉과 일체된 조명장치의 필요성이 항상 제기되어 왔던 문제이다. 본 논문에서는 이러한 문제점에 주안을 두고 조작봉과 일체된 전계검출에 의한 발광동작을 제어할 수 있는 발광형 COS 조작봉에 대해 각각의 구성별 요소들을 분석하고자 한다.

• Proceedings of the Korean Society of Precision Engineering Conference
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• 2000.11a
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• pp.639-642
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• 2000