• 한국지진공학회:학술대회논문집
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• 한국지진공학회 1997년도 춘계 학술발표회 논문집 Proceedings of EESK Conference-Fall 1997
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• pp.217-224
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• 1997

The safety related equipments for use in nuclear power plants should be subjected to the seismic qualification in order to insure the safety of the nuclear power plant. This paper summarizes the seismic qualification test on the Low Voltage Motor Control Centers(MCC's) for use in Wolsong Nuclear Power Plants, Units 2, 3 and 4. The seismic qualification test was performed on the two prototype MCC's(a two-bay wide unit for Phase #1 Test and a five-bay wide unit for Phase #2 Test). The specimens were electrically powered and monitored during the test process. It was demonstrated that the specimens possessed sufficient structural and electrical integrity to withstand the required seismic conditions.

• Nuclear Engineering and Technology
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• 제31권1호
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• pp.58-67
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• 1999

The purpose is to produce a model of nuclear reactor trip logic caused by the steam generator water level of Wolsong 2/3/4 unit through an activity chart and a statechart and to produce C language automatically using Statechart-based Formalism and Stalemate MAGNUM toolset suggested by David Harel Formalism. It was worth attempting auto-generation of C language though we manually made Software Requirement Specification(SRS) for safety-critical software using statechart-based formalism. Most of the phases of the software life-cycle except the software requirement specification of an analysis phase were generated automatically by Computer Aided Software Engineering (CASE) tools. It was verified that automatically produced C language has high productivity, portability, and quality through the simulation.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1998년도 춘계학술발표회논문집(1)
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• pp.315-320
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• 1998

In this work, an automatic software verification method for Nuclear Power Plant (NPP) protection system is developed. This method utilizes Colored Petri net (CPN) for modeling and Prototype Verification system (PVS) for mathematical verification. In order to help flow-through from modeling by CPN to mathematical proof by PVS, a translator has been developed in this work. The combined method has been applied to a protection system function of Wolsong NPP SDS2(Steam Generator Low Level Trip)and found to be promising for further research and applications.

• 방사성폐기물학회지
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• 제19권2호
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• pp.177-186
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• 2021

Radioactive materials from nuclear power facilities can be released into the atmosphere through various channels. Recently, the dispersion of radioactive materials has become critical issue in Korea after Kori Unit 1 and Wolsong Unit 1 were permanently shut down. In this study, annual atmospheric dispersion factors were compared based on the continuous release and purge release using the XOQDOQ computer program, a method for calculating atmospheric dispersion factors at commercial nuclear power stations. The meteorological data analyzed in this study was based on the Shin Kori nuclear power meteorological tower which has the largest operating nuclear power plants in Korea, for three years (from 2008 to 2010). The analysis results of the dispersion factor of the radioactive material release obtained using the XOQDOQ program showed that the difference between the continuous release and purge release was within two times. This study will be valuable helpful for revealing the uncertainty of the predictive atmospheric dispersion factor to achieve regulation.

• 방사성폐기물학회지
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• 제12권4호
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• pp.315-334
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• 2014

월성원자력환경센터 중저준위방사성폐기물 처분시설은 서로 다른 방식의 처분시설이 혼재하고, 월성 원자력발전소와도 인접해있다. 이와 같은 높은 복잡성으로 인해 처분시설 안전성 평가 시 보다 면밀한 현상이해가 필요하다. 기존 1단계 사일로 처분시설의 성능평가모델들에 포함된 불필요한 보수성을 줄이고 복합처분시설에 대한 보다 실제적인 성능을 파악하기 위해서는 다차원 수리/핵종이동 모델이 필요하다. 이와 함께 향후 복합처분시스템의 특성에 기인한 다양한 불확실성을 관리하고 파라미터의 중요도를 분석하기 위해 많은 계산이 필요할 것으로 예상하며, 이를 위해 보다 효율적인 성능평가 모델이 요구된다. 본 논문에서는 두 요건을 충족시키기 위해 수리성능 모델과 핵종이동 모델을 연계한 2단계 천층처분시설의 근계영역 2차원 통합성능평가 모델을 개발하였다. 수리 및 핵종이동은 PORFLOW와 GoldSim 전산 코드를 이용해 평가하였으며, GoldSim 핵종이동 모델은 PORFLOW 핵종이동 모델과의 벤치마크를 통해 검증하였다. GoldSim 모델은 계산효율이 뛰어났으며 기존의 모델에 비해 핵종이동거동을 이해하는데 용이하였다.

• 방사성폐기물학회지
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• 제11권4호
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• pp.311-324
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• 2013

우리나라 중저준위 방사성폐기물 최종 처분시설인 월성원자력환경관리센터의 폐쇄 후 안전평가 컴퓨터 프로그램의 신뢰성 확보를 위해 MASCOT와 검증프로그램으로 SAFE-ROCK와 GOLDSIM을 선정하여 정상시나리오에 대하여 안전평가를 수행하였다. 각 프로그램의 장단점을 비교/분석하였으며, 각 프로그램 별 구획 간의 선량 및 누출량을 평가하였다. 그 중 방사성핵종 $^{129}I$와 $^3H$가 MASCOT와 SAFE-ROCK 프로그램에서는 비슷한 경향을 보여주었지만, GOLDSIM 프로그램에서는 상이한 결과를 나타냈다. 이는 각 프로그램의 근계지역 내 핵종이동방정식의 해석과정의 차이와 개별 프로그램의 한계로 인해 다른 결과값을 보여주는 것으로 분석되었다. GOLDSIM 프로그램의 경우, 선원항 구획에서 초기 핵종누출량은 time-scale에 민감하게 반응한다는 사실도 확인할 수 있었다. 안전평가 프로그램은 처분환경에서 발생하는 핵종거동 및 이동에 대한 실제현상을 예측하기 위해 모델링을 거치지만, 전산프로그램의 특성과 실제현상에 대한 데이터가 제한적이므로 결과에 차이가 발생하게 된다. 이러한 차이점은 다양한 프로그램을 이용한 결과와 상호비교를 통해 알아내며 그 원인을 지속적으로 분석하는 연구개발과정을 필요로 하고 있다.

• 제어로봇시스템학회:학술대회논문집
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• 제어로봇시스템학회 2003년도 ICCAS
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• pp.1220-1224
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• 2003

In this paper, we measured the radiation dose of a fuel handling machine of the CANDU type Wolsong nuclear reactor directly during operation, in spite of the high radiation level. In this paper we will describe the sensor development, measurement techniques, and results of our study. For this study, we used specially developed semiconductor sensors and matching dosimetry techniques for the mixed radiation field. MOSFET dosimeters with a thin oxide, that are tuned to a high dose, were used to measure the ionizing radiation dose. Silicon diode dosimeters with an optimum area to thickness ratio were used for the radiation damage measurements. The sensors are able to distinguish neutrons from gamma/X-rays. To measure the radiation dose, electronic sensor modules were installed on two locations of the fuel handling machine. The measurements were performed throughout one reactor maintenance cycle. The resultant annual cumulative dose of gamma/X-rays on the two spots of the fuel handling machine were 18.47 Mrad and 76.50 Mrad, and those of the neutrons were 17.51 krad and 60.67 krad. The measured radiation level is high enough to degrade certain cable insulation materials that may result in electrical insulation failure.

• 한국압력기기공학회 논문집
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• 제6권1호
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• pp.78-82
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• 2010

The feeder pipe of Main Primary Heat Transfer System in Wolsong Nuclear Power Plant was inspected by the Ultrasonic Phase Array technique in 2010. It is the first time to apply this method to the construction at Nuclear Power Plant in Korea. The time required for UT technique is less than RT method. The UT method doesn't need to evacuate personnel who works nearby inspecting area and doesn't need to wait developing of film. For these reasons, the UT method is the fastest method among the volumetric inspections. As a result of the examination, it became clear that main defect of the feeder pipe is the Lack of fusion in the welded area. Moreover, the rate of defect was reduced gradually as improvement of welder's skill. If welding machine has problem, the defect has tended to same pattern(occurred same position in the welding area) but these defects were founded without specific rules. For these reasons, the creation of defect is dependent on the skill of worker not on the automatic welding machine. This evaluation of defect signal and collecting data would be useful to further examination in ISI.

• 환경생물
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• 제30권3호
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• pp.173-184
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• 2012

In order to investigate the fluctuation rates [FR] of phytoplankton after passage through a cooling system, the standing crops, chlorophyll a concentrations and carbon assimilation number of phytoplankton were surveyed at intake and outlet at Wolsong nuclear power plant [NPP] from July 2006 to June 2008. As a result, the total mean standing crops of phytoplankton were $1.0{\times}10^6\;cells\;L^{-1}$ and $7.3{\times}10^5\;cells\;L^{-1}$ at intake and outlet, respectively. The FR of phytoplankton by passage through the cooling system [PTCS] was 27.0%. Among them, the FR of microplankton and nanoplankton were 34.1% and 12.4%, respectively. In addition, the FR of diatoms and dinoflagellateswere 33.9% and 29.7%, respectively. These results showed the entrainment effects on microplankton and diatoms by PTCS were higher than those of nanoplankton and dinoflagellates. The FR of total chlorophyll a concentrations were 54.4%, and the FR of microplankton, nanoplankton and picoplankton were 58.9%, 38.5%, and 52.4%, respectively. So the entrainment effects on microplankton by PTCS were higher than those of nanoplankton and picoplankton. The mean FR of carbon assimilation number of phytoplankton was 57.6%, and the seasonal variations of FR of carbon assimilation number ranged from 47.5% to 76.8%. Our results indicated that the phytoplankton species responded differently to power plant operating conditions such as elevated temperature, chlorination, and mechanical impacts.

• Nuclear Engineering and Technology
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• 제31권2호
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• pp.157-171
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• 1999

In this work, an automatic software verification method for Nuclear Power Plant (NPP) protection system is developed. This method utilizes Colored Petri Net (CPN) for system modeling and Prototype Verification System (PVS) for mathematical verification. In order to help flow-through from modeling by CPN to mathematical proof by PVS, an information extractor from CPN models has been developed in this work. In order to convert the extracted information to the PVS specification language, a translator also has been developed. ML that is a higher-order functional language programs the information extractor and translator. This combined method has been applied to a protection system function of Wolsong NPP SDS2(Steam Generator Low Level Trip). As a result of this application, we could prove completeness and consistency of the requirement logically. Through this work, in short, an axiom or lemma based-analysis method for CPN models is newly suggested in order to complement CPN analysis methods and a guideline for the use of formal methods is proposed in order to apply them to NPP Software Verification and Validation.