• Journal of Energy Engineering
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• v.25 no.1
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• pp.15-22
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• 2016

The heat transport system transients of Wolsong 2,3,4 nuclear power plants were analysed during abnormal operating conditions. The compliance with requirements of AECB Regulatory Document R-77 for CANDU reactor was estimated. The analysis results showed that for each postulated accident the peak pressure values in the reactor headers are within the acceptance criteria given in ASME code requirements. The effect of LRV that is one of the overpressure protection device was very minor.

• Nuclear Engineering and Technology
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• v.28 no.5
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• pp.500-505
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• 1996

At the reference plant(Wolsong unit No. 1) a manual poison sampling system is provided to periodically sample gadolinium from each tank and analyze it in the laboratory to provide assurance that adequate poison concentration in each tank is maintained. The AECB required a continuous, on-line monitoring system. On Wolsong unit No. 2, process piping adapter and new instrument loops added to the Liquid Injection Shutdown System(LISS) which is part of SDS2. The new instrument loops continuously monitor SDS2 poison conductivity and initiate an alarm when the poison concentration is too low.

• Proceedings of the KIEE Conference
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• 2001.07a
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• pp.28-34
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• 2001

월성2호기가 100% 출력 운전중 2001.4.6일 20:16분에 345kV 신경산변전소 GIS모선#1측 지락고장 파급으로 주발전기 정지중 기동시 보호 용계전기(50/27)가 동작되어 발전정지 되고 원자로 출력은 60%까지 감발 되었음. 본 보호계전기는 발전기 정지나 터닝기어로 저속운전 중 인적 실수에 의해 발전기 병입용차단기 투입시 발전기가 과도한 돌입전류로 손상되는 것을 방지하기 위한 계전기로, 정상운전중이거나 외부사고시에는 동작할 수 없는 보호계전기임. 따라서 본 보호계전기의 동작원인을 당시 동작 상황과 기록데이터를 정정치와 함께 분석하고 적정동작을 위한 대책을 제시함.

• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.67.1-67
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• 2001

• Proceedings of the Korean Nuclear Society Conference
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• 2003.05a
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• pp.263.2-263.2
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• 2003

• Proceedings of the Korean Nuclear Society Conference
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• 2003.05a
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• pp.294.2-294.2
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• 2003

• Proceedings of the Korean Nuclear Society Conference
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• 2003.05a
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• pp.440.2-440.2
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• 2003

• Proceedings of the Korean Nuclear Society Conference
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• 2003.10a
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• pp.445.2-445.2
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• 2003

• Transactions of Materials Processing
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• v.8 no.3
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• pp.241-241
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• 1999

With the aim of assessing the degradation of Zr-2.5Nb pressure tubes operating in the Wolsong unit-1 nuclear power plant, characterization tests are being conducted on irradiated Zr-2.5Nb tubes removed after 10-year operation. The examined tube had been exposed to temperatures ranging from 264 to 306℃ and a neutron fluence of 8.9×$10^{21}$ n/cm²(E>1 MeV) at the maximum. Tensile tests were carried out at temperatures ranging from RT to 300℃. The density of a-type and c-type dislocations was examined on the irradiated Zr-2.5Nb tube using a transmission electron microscope. Neutron irradiation up to 8.9×$10^{21}$ n/cm²(E>1 MeV) yielded an increase in a-type dislocation density of the Zr-2.5Nb pressure tube to 7.5×$10^{14} m^{-2}$, which was highest at the inlet of the tube exposed to the low temperature of 275℃. In contrast, the c-component dislocation density did not change with irradiation, keeping an initial dislocation density of 0.8×$10^{14} m^{-2}$ over the whole length of the tube. As expected, the neutron irradiation increased mechanical strength by about 17-26% in the transverse direction and by 34-39% in the longitudinal direction compared to that of the unirradiated tube at 300℃. The change in the mechanical properties with irradiation is discussed in association with the microstructural change as a function of temperature and neutron fluence.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05b
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• pp.643-648
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• 1996

Recent failures of Heat Transport (HT) system Liquid Relief Valves (LRVs) at several CANDU 6 plants resulted in heavy water spills. A multi-discipline KAERI task team along with AECL representatives was set up to assess the specific implications on the Wolsong 2/3/4 station. The study applied the knowledge gained from the generic study by conducting a fundamental review of the specific design of Welsong 2/3/4. The purpose of the study was to demonstrate compliance with the relevant codes and licensing regulations and to identify the improvements to the design and operating procedures applicable to Wolsong 2/3/4. This paper presents the key recommendations of this study.