• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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• 2007.11a
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• pp.1386-1390
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• 2007

This paper presents the equipment condition monitoring technology for the process or the equipment using statistical techniques. The equipment condition monitoring system consists of an empirical model to estimate the expected sensor values of process variables and a diagnose model to detect the abnormal condition and to identify the root source of the problem. The empirical model is constructed by the analysis of historic data. The diagnose model uses the sequential probability ratio test (SPRT) technique. The monitoring system was tested with real operating data acquired from the Reactor Coolant Pump Seal in the Nuclear Power Plant. It can detect the system degradation or failure at the early stage since it is able to catch the subtle deviation of process variables from normal condition.

• Proceedings of the KIEE Conference
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• 2011.07a
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• pp.1760-1761
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• 2011

원자력발전기술원은 발전정지 관련계통 제어케비넷 내에 장착된 제어용 기기들의 다중화 설계변경 활동을 지원하고 관련 기기의 배선상태 등의 육안점검을 통해 취약성 여부를 최종 확인하기 위하여 국내 Westinghouse형 원전 계측제어 케비넷 점검을 수행하였다. 또한 관련 설계변경에 대한 신뢰도평가 기술지원도 함께 수행하여 해당 설계변경이 설비의 신뢰도 향상에 효과가 있는지를 정량적으로 평가하고자 하였다. 이에 따라 원자로냉각재펌프(RCP, Reactor Coolant Pump) 제어 채널의 다중화 개선에 대하여 설계변경 전후의 기기 배열 변화에 따른 계통 신뢰도 변화를 대표유형 기기의 고장률에 근거하여 분석하였다. 고장수목을 이용하여 설계변경 전후의 RCP 고장정지로 인한 발전정지를 유발하는 고장조합을 도출하고, 고장정지 확률 변화를 정량화 하였다. 또한 기기 보호 측면에서 펌프 보호를 위한 신호를 출력하지 못하는 경우를 정량화하여 이를 비교하였다.

• KIEE International Transaction on Electrical Machinery and Energy Conversion Systems
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• v.3B no.1
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• pp.32-36
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• 2003

The three-phase canned induction motor, which consists of a stator and rotor with a seal can, is used for the main coolant pump (MCP) of the System-integrated Modular Advanced Reactor (SMART). The thermal characteristics of the can must be estimated exactly, since the eddy current loss of the can is a dominant parameter in design. Besides the insulation of the motor winding is compared of Teflon, glass fiber, and air, so it is not an easy task to analyze. A FEM thermal analysis was per-formed by using the thermal properties of complex insulation which were obtained by comparing the results of finite element thermal analysis and those of the experiment. As a result, it is shown that the characteristics of prototype canned induction motor have a good agreement with the results of FEM.

• Journal of KSNVE
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• v.8 no.4
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• pp.723-732
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• 1998

원자력 발전소에서 운전되고 있는 원자로 냉각재 펌프는 대형 수직 펌프로서 증기 발생기로부터 원자로에 냉각재를 순환시키는 중요한 역할을 담당하고 있다. 원자로 냉각재 펌프는 운전 조건 및 각종 결함에 따라 진동, 열적 변형, 마모 등의 비정상 상태에서 운전될 수 있으며, 이로 인한 발전소 신뢰성 저하의 원인이 된다. 따라서 이 펌프의 감시 및 진단에 대한 연구가 계속되어 왔으며 각종 시스템이 설치 운용되고 있다. 그러나 미국내의 거의 모든 냉각재 펌프 감시 시스템은 펌프의 고진동 여부만을 나타내며 진동의 원인을 진단하기 어렵다. 본 연구에서는 최근까지 주로 발생되었던 미국내 원자로 냉각재 펌프의 문제점을 분석하고 이들의 원인별 진동 특성을 지식베이스화 하였으며, 진단시스템 개발을 위한 알고리즘을 제안하였다.

• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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• 2011.10a
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• pp.221-226
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• 2011

The structural integrity of APR1400 reactor vessel internals has been being assessed referring the US Nuclear Regulatory Commission regulatory guide 1.20 comprehensive vibration assessment program. The program is composed of a vibration and stress analysis, a limited vibration measurement, and an inspection. This paper covers the vibration and stress analysis on the reactor vessel internals due to the pulsation of reactor coolant pump. 3-dimensional models to calculate the hydraulic loads and structural responses were built and the pressure distributions and the structural responses were predicted using ANSYS. The peak stress of the reactor vessel internals is much lower than the acceptance limit.

• Proceedings of the KIEE Conference
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• 1999.07a
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• pp.308-311
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• 1999

A squirrel cage canned induction motor for the main coolant pump of the integral reactor, SMART was designed, manufactured and tested. The motor was first designed using the equivalent circuit theory to determine major dimensions and then finalized through finite element analyses for electromagnetic and thermal characteristics. In order to verify the design methodology, a reduced scale canned induction motor was manufactured and tested. The experimental results have shown a good agreement with the analysis results.

• International Journal of Fluid Machinery and Systems
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• v.10 no.2
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• pp.138-145
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• 2017

The problem of non-uniform inflow exists in many practical engineering applications, such as the elbow suction pipe of waterjet pump and, the channel head of steam generator which is directly connect with reactor coolant pump. Generally, pumps are identical designs and are selected based on performance under uniform inflow with the straight pipe, but actually non-uniform suction flow is induced by upstream equipment. In this paper, CFD approach was employed to analyze unsteady hydrodynamic characteristics of reactor coolant pumps with different inflows. The Reynolds-averaged Naiver-Stokes equations with the $k-{\varepsilon}$ turbulence model were solved by the computational fluid dynamics software CFX to conduct the steady and unsteady numerical simulation. The numerical results of the straight pipe and channel head were validated with experimental data for the heads at different flow coefficients. In the nominal flow rate, the head of the pump with the channel head decreases by 1.19% when compared to the straight pipe. The complicated structure of channel head induces the inlet flow non-uniform. The non-uniformity of the inflow induces the difference of vorticity distribution at the outlet of the pump. The variation law of blade to blade velocity at different flow rate and the difference of blade to blade velocity with different inflow are researched. The effects of non-uniform inflow on radial forces are absolutely different from the uniform inflow. For the radial forces at the frequency $f_R$, the corresponding amplitude of channel head are higher than the straight pipe at $1.0{\Phi}_d$ and $1.2{\Phi}_d$ flow rates, and the corresponding amplitude of channel head are lower than the straight pipe at $0.8{\Phi}_d$ flow rates.

• Proceedings of the KIEE Conference
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• 1994.07b
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• pp.1431-1434
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• 1994

The annular induction electromagnetic pump with maximum flowrate of $60{\ell}/min$ for the sodium coolant system of liquid metal fast breeder reacters has been designed using the equivalent circuit method. The final optimum values of geometrical and electromagnetic parameters were obtained for an annular induction pump from the relation of the electrical variables giving the developing force to the fluid and the pressure drops between both sides of the pump. The physical properties of the core, coil condoctor materials in the high temperature and pump cooling systems under operation have been taken into account in the design of the pump. The structural material were also selected considering the reaction with sodium and the magnetic field distortion.

• Proceedings of the Korean Nuclear Society Conference
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• 2001.10a
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• pp.254.2-254
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• 2001

• Proceedings of the Korean Nuclear Society Conference
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• 2001.10a
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• pp.358.1-358
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• 2001