• Journal of the Society of Disaster Information
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• v.8 no.2
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• pp.188-196
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• 2012

Dynamic parameters such as natural frequencies can provide global stiffness information of a structure, and thus be utilized in monitoring structural integrity of large structures such as a containment. To identify the dynamic parameters without interrupting normal operation, a modal analysis method based on ambient vibration measurements should be applied. In this study, dynamic parameters of the containment of Wolsong Unit 2 are identified using ambient vibration measurement data. The feasibility of the study is verified using a numerical model for the containment. From the modal analysis, dynamic parameters of the containment with acceptable correlation to analytical modes can be estimated.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.17 no.2
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• pp.235-243
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• 2019

Radioactive materials are released into the air and deposited on the surface soil after a nuclear accident. Radionuclides deposited in soil are transported by precipitation to nearby environments and contaminate the surface water system. Basic data on surface watershed and soil erosion models have been collected and analyzed to evaluate the behavior of radionuclides deposited on surface soil after a nuclear accident. Data acquisition and analysis in aquatic environment were performed to investigate the physical characteristics and variation of biota in rivers and lakes of the Nakdong river area near the Wolsong nuclear power plant. For these purposes, a digital map, and hydrological, water quality and biota data were gathered and a systematic database (DB) was constructed in connection with them. Constructed aquatic DB will be supplied and used in surface watershed and soil erosion models for investigation of long-term movement of radionuclides in adsorptive form in surface soil. Finally, basic data and established models will be utilized for general radiological impact assessment in aquatic environment.

• Proceedings of the Korea Institute of Applied Superconductivity and Cryogenics Conference
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• 2001.02a
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• pp.163-166
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• 2001

KEPCO has a plan to construct TRF (tritium removal facility) in wolsong nuclear power plant site by 2005. In advance of WTRF construction, the pilot plant was installed at KEPRI in order to show process reliability of WTRF. The main processes of this pilot plant are LPCE(liquid phase catalytic exchange) and CD (cryogenic distillation). Deuterium is separated from heavy water in LPCE process and concentrated in CD process. CD process consists of cold box, where are a distillation column and heat exchangers, vacuum system, cryogenic refrigerant supply system and instrument & control system. The experience of the pilot plant will be used in WTRF design review, operating procedure revision and fundamental education for the operators.

• Journal of Power System Engineering
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• v.11 no.3
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• pp.3-8
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• 2007

The emergency AC power supply system of the nuclear power plant is designed to supply the power to the nuclear reactor at the emergency operating condition. The safety function of the diesel generator at the nuclear power plant is to supply AC electric power to the plant safety system whenever the preferred AC power supply is unavailable. The reliable operation of onsite emergency diesel generator should be ensured by a conditioning monitoring system designed to maintain and monitor and forecast the reliability level of diesel generator. To do this kind of diesel generator condition monitoring we reviewed several operating factors and history of the wolsong unit 3 diesel generator and selected the proper conditioning monitoring operating factors.

• Proceedings of the IEEK Conference
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• 1999.06a
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• pp.1083-1086
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• 1999

중수로(CANDU) 형 월성 원자력발전소의 칼란드리아 압력관 전면부를 감시점검하기 위한 열영상 관측시스템을 설계/제작하였다. 중수로는 가동중에 핵연료를 교체한다. 칼란드리아 전면부에는 380 개의 압력관 채널이 위치하고 있다. 핵연료를 교체할 시에 핵연료 교체장비가 칼란드리아 압력관 채널의 ENDCAP을 열고 핵연료를 장전하는 과정에서 발생할 지도 모르는 중수누출, 핵연료교체장비의 이상상태를 점검하는데 목적이 있다. 열영상카메라는 상용 CCD 카메라에 비해 영상의 해상도가 떨어진다. CCD 카메라는 수증기 누출과 같은 육안검사에 활용하고, 열영상카메라는 압력관 채널의 온도변화 등을 점검하기 위해 CCD/열영상카메라의 융합구조로 설계/제작하였다.

• Proceedings of the IEEK Conference
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• 1999.06a
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• pp.1087-1090
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• 1999

중수로(CANDU) 형 월성 원자력발전소의 칼란드리아 압력관 전면부를 감시점검하기 위한 열영상 관측프로그램을 개발하였다. 국내의 사용자들의 요구에 부응할 수 있는 다양한 기능을 부가 하였다. 부가된 기능에는 임의의 포인트, 영역, 라인, 경계선을 마우스로 지정하여, 선택된 지점, 영역, 라인 및 경계선의 특징을 추출할 수 있는 기능을 갖추고 있다. 또한 KAERI Thermo Inspector 의 기능을 살린 일반영상/열영상의 매핑기능을 부가하였다. 일반영상에 비해 상대적으로 해상도가 떨어지는 열영상대신에 CCD 영상의 관측포인트를 지정하면 열영상카메라좌표계의 매핑된 지점의 이상상태를 판정할 수 있는 특성을 갖는다.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05b
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• pp.579-585
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• 1996

A CATHENA model for the reactor regulating system is developed and tested independently. A CATHENA plant model is created by combining this model with the reference CATHENA model which has been developed to analyze a loss-of-coolant accident (LOCA) for the Wolsong 2 generating station. This model is intended to provide a trip coverage analysis capability. The CATHENA reactor regulating system model includes the demand power routine. the light water zone control absorbers, mechanical control absorbers and adjusters. The CATHENA model is tested for steady state at 103% full power. A postulated accident transient (small LOCA) was also tested. The results show that the control routines in CATHENA were set up properly.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05b
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• pp.213-218
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• 1996

A simulation model for the transient behavior of CANDU U-tube steam generator(UTSG) has been developed for application to the simulation of operational transient behavior of CANDU nuclear power plant. For application to CANDU UTSG. tile design characteristics of CANDU UTSG such as Wolsong Units, feedwater inlet near the tube sheet. is approximated. For realistic prediction of thermal hydraulic behavior of and tube bundle region is divided into two separate control volumes, subcooled region and saturated region. and the variation of thermal hydraulic properties within a control volume is considered. Test results for typical CANDU operational transient case show reasonable transient behavior of steam generator and considered to be applicable to the simulation of overall plant.

• Proceedings of the Korean Institute of Building Construction Conference
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• 2018.05a
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• pp.230-231
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• 2018

Recently, the danger for radioactive materials has become a hot topic. Beginning with the Chernobyl nuclear accident in 1996, in 2011, the Fukushima nuclear power plant in Japan suffered major damage such as large-scale casualties and radioactive dangerous area selection. Concerns about leakage of radioactive materials due to recent earthquakes have been deepening in Korea, such as Wolsong Nuclear Power Plant in Gyeongju, and there is a growing interest in the safety of radioactive materials through the media and the media. However, the route to exposure to radioactive materials is not limited to these large-scale nuclear accidents. Typical examples of this are radioactive substances exposed in daily life. In the case of radon gas, the danger is being revealed through current events programs and news, and natural radiation exposure is attracting attention.

• Proceedings of the KIEE Conference
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• 1999.07e
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• pp.2110-2113
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• 1999

This paper describes the initial characteristics of turbine generators at the Taean thermal power plant #4 and Wolsong nuclear power plant #2. The turbine generators had been in service for two years. The insulation diagnostic tests included measurements of insulation resistance, polarization index, ac current, dissipation factor($tan{\delta}$) and partial discharges (PD). The values of ac current and tan a were measured by Schering bridge. PD measurements were conducted using digital PD detector. The variation of $tan{\delta}$ and PD was confirmed in two generator stator insulations.