• JOURNAL OF ELECTRICAL WORLD
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• s.412
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• pp.66-67
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• 2011

우리나라는 원자력발전 3대 핵심기술인 원전계측제어시스템(MMIS), 원자로냉각재펌프(RCP), 원전설계핵심코드의 국산화를 추진하고 있다. 지난해 가장 먼저 MMIS가 국산화에 성공했으며, IAEA로부터 우수성을 평가받을 정도로 기술적 우위를 확보했다. 원전설계핵심코드 중 노심설계코드도 2010년에 개발을 완료하였다. RCP도 일부 구성품은 이미 국산화에 성공하였으며, 2012년에 순수 국산제품 개발이 완료될 예정이다.

• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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• 2013.04a
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• pp.581-582
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• 2013

• Journal of Welding and Joining
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• v.9 no.2
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• pp.1-10
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• 1991

용접대상으로서 가장 중요한 것은 원자로의 구조재료이며 이것에는 원자력 용기, 중기 탱크, 액 체연료용기, 연료봉 피복, 제어봉피복, 냉각재 도관 및 출력 계통의 각종 도관, 열교환기, 펌프, 밸브 등의 구조재료 및 원자로의 부대 설비로서의 연료 화학처리 과정등에 사용되는 각종 금속 재료가 있다.

• The KSFM Journal of Fluid Machinery
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• v.14 no.1
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• pp.18-23
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• 2011

The hydraulic part in reactor coolant pump consists of suction nozzle, impeller, diffuser, and discharge nozzle. Among them, impeller is required to be designed to satisfy performance requirements such as head, NPSHR, and head curve slope at design point. Present study is intended to suggest the preliminary design method sizing the impeller size to satisfy the design requirement particularly including head curve slope at design point. On a basis of preliminary design result, hydraulic components have been designed in detail by CFD and then manufactured in a reduced scale. Experiment in parallel with computational analysis has been executed in order to confirm the hydraulic performance. Comparison results show good agreement with design result, confirming the validity of design method suggested in this study.

• Journal of Advanced Marine Engineering and Technology
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• v.31 no.1
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• pp.84-94
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• 2007

As a reactor coolant pump(RCP) is operated in the nuclear power system for a long time. so its surface is continuously contaminated by radioactive scales. In order to perform regular or emergency repair about RCP internals a special decontamination process should be used to reduce the radiation from the RCP surface by means of chemical cleaning. In this study, applicable possibility in chemical decontamination for RCP was investigated on the various materials. The STS 304 showed the best electrochemical properties for corrosion resistance than other materials. However, the pitting corrosion was slightly generated in both STS 415 and STS 431 with the increasing numbers of cycle and intergranular corrosion were sporadically observed. The size of their pitting corrosion and intergranular corrosion were also increased with increasing cycle numbers.

• 유체기계공업학회:학술대회논문집
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• 1999.12a
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• pp.245-251
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• 1999

The structural analysis of a reactor coolant pump(RCP) of a nuclear power plant is very important for the safety assessment of the plant. Accurate boundary conditions for the heat transfer coefficient are required for reliable thermal stress analysis of the pump casing, especially in transient operations of the pump since the coolant properties are largely dependent on operational conditions. In the present study, a 3D mixed flow type coolant pump was modeled from the RCP drawings and analyzed in the steady state and number of transient flow conditions by using a commercial code STAR-CD. From the result of the computation, it is seem that the average heat transfer coefficients for the cases considered are found to be the suggested values of the manufacturer, Westinghouse Energy System. The unevenness in local heat transfer coefficients, however, is found to be considerable so that the use of average heat transfer coefficients in all boundaries might not give reliable thermal stresses.

• Nuclear Engineering and Technology
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• v.22 no.2
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• pp.128-138
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• 1990

This paper presents a prototype expert system (ESRCP) for Reactor Coolant Pumps. The purpose of this system is to diagnose RCP failures and to offer corrective operational guides to plant operators. The first symptoms for the diagnosis are the alarms which are related to the RCP domain. Alarm processing is required to find a primary causal alarm when multiple alarms occur. The system performs the alarm processing by rule-based deduction or priority factor operation. To diagnose the RCP failure, the system performs rule-based deduction or Bayesian inference. Various sensor readings are required as symptoms to infer a root cause. When the symptoms are insufficient or uncertain to diagnose accurately, Bayesian inference is performed.

• Proceedings of the Korean Nuclear Society Conference
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• 2004.05a
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• pp.151.2-151.2
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• 2004

• Proceedings of the Korean Nuclear Society Conference
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• 2003.10a
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• pp.475.1-475.1
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• 2003

• Proceedings of the KIEE Conference
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• 2011.07a
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• pp.1999-2000
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• 2011

본 연구의 목적은 발전소의 정상적인 출력운전을 위해 필요한 주요 계통의 기능에 영향을 미쳐 발전소 불시정지를 유발할 수 있는 핵심 기기, 즉, 발전정지유발기기의 설치 개소를 체계적인 방법을 통하여 정밀 분석하고, 해당 기기의 고장모드와 그 영향을 검토하여 이를 방지하기 위한 대책을 수립하도록 하는 것이다. 발전정지유발기기의 평가는 발전소 종사자로 하여금 가동 중 발전소에서 발생 가능한 발전정지 영향기기와 그들의 상호관계를 이해하고, 정량적 평가를 통해 해당기기들의 발전소 발전정지 영향을 시각적으로 확인하여 불시 발전정지를 예방할 수 있는 대응 논리를 인지할 수 있도록 하는데 그 목적이 있다. 원자로냉각재계통에 대한 발전정지유발기기(SPV, Single Point Vulnerability)를 분석하기 위해 고장모드영향분석(FMEA, Failure Mode Effect Analysis)을 수행하고 상세 고장수목을 개발하여 통합단위의 계통 분석을 수행하였다. 분석결과 원자로냉각재계통의 발전정지유발기기는 원자로냉각재 펌프와 가압기 주살수 밸브의 제어회로에 집중되어 있는 것으로 나타났다.