• Journal of Radiation Protection and Research
• /
• v.33 no.2
• /
• pp.67-76
• /
• 2008

As the first comprehensive attempt at a national implementation, this study aims at assessing the external costs of major electricity generation technologies in Korea, particularly an evaluation of the impacts on human health resulting from exposures to atmospheric radiological emissions from nuclear power plants, and a monetary quantification of their damages. The methodology used for the assessment of the externalities of the selected fuel cycles has been developed by the International Atomic Energy Agency (IAEA), namely the SimPacts Model Package. The model is internationally recognized as a tool which can be applied to a wide range of fuels, different technologies and locations, for an externalities study. In this study, the relevant emissions are quantified first and then their impacts on human health are evaluated and compared. The study focused on all the nuclear power plants for the last 6 years ($2001{\sim}2006$) in Korea. With respect to nuclear power, the impact analysis only focuses on a power generation, however the front- and back-end nuclear fuel cycles are not included, namely uranium mining, conversion, enrichment, reprocessing, conditioning, etc., because these facilities are not present in Korea. The analysis results show that nuclear power in general, generates low external costs. The highest damage costs from the nuclear power plants among the 4 sites in Korea were estimated to be 3.9 mills/MWh, which is about 1/20th of the result for a similar case study conducted in the U.K., implemented through the ExternE project. This difference is largely due to the number of radionuclides included in the study and the amount of released radioactive emissions based on up-to-date information in Korea. In this study, the sensitivities of the major factors for nuclear power plants were also calculated. The analysis indicates that there was around a ${\pm}3%$ damage costs variation to a ${\pm}15%$ change of the reference population density and a ${\pm}1%$ damage cost variation to a $1{\sim}30$ meters change of the effective release height, respectively. These sensitive calculations show that there is only a minor difference when the reference costs are compared.

• Journal of Radiation Protection and Research
• /
• v.20 no.4
• /
• pp.285-296
• /
• 1995

The site of Korea Final Repository, KFR, to collect and dispose of radioactive wastes produced in nuclear power plants will be selected to seaside. As all the radwastes stored temporarily in the site of power plants should be transported by the sea, Nuclear Environmental Management Center, NEMAC, of Korea Atomic Energy Research Institute, KAERI, has been developing the sea transport system to secure safe and efficient transportation of the radwastes from the power plant sites to the final repository. Investigating the status of advanced techniques of foreign countries for transport vessels and considering inland circumstances, the technical criteria of the transport vessel have been suggested in this study. Therefore, all the radwastes will be transported safely by the sea, without releasing any radioactive material to environment even in the case of accident.

• Journal of the Earthquake Engineering Society of Korea
• /
• v.8 no.6 s.40
• /
• pp.23-29
• /
• 2004

The design earthquake used for the seismic analysis and design of NPP (Nuclear Power Plant) is determined by the deterministic or probabilistic methods. The probabilistic seismic hazard analysis(PSHA) for the nuclear power plant sites was performed for the probabilistic seismic risk assessment. The probabilistic seismic hazard analysis for the nuclear power plant site had been completed as a part of the probabilistic seismic risk assessment. The probabilistic method become a resonable method to determine the design earthquakes for NPPs. In this study, the defining method of the probability based scenario earthquake was established, and as a sample calculation, the probability based scenario earthquakes were estimated by the de-aggregation of the probabilistic seismic hazard. By using this method, it is possible to define the probability based scenario earthquakes for the seismic design and seismic safety evaluation of structures. It is necessary to develop the rational seismic source map and the attenuation equations for the development of reasonable scenario earthquakes.

• Nuclear industry
• /
• v.36 no.11
• /
• pp.29-44
• /
• 2016

1980~1990년대 OPR1000 기술 자립을 추진할 때도 그랬지만 한국은 원자력 기술 자립에 대한 도전이 선진국에 비해 늦었지만 과학기술자의 열정과 정부의 적극적인 지원으로 오늘날 원자력 선진국이 될 수 있었고, 원자력산업을 해외 수출 산업으로서 다양한 노력을 시도하고 있다. 특히 국내 가동 중인 원전은 외국과 차별되게 1기당 고장 정지율이 0.1건으로 외국 평균의 5.5건과 크게 대별된다. 또한 운전 신뢰성을 나타내는 발전소 가동률도 10% 이상 차로 월등히 높다. 한마디로 한국은 가장 원전의 기술 개발과 운영을 잘하고 있는 원전 선진국임을 자타가 인정하고 있다. 그러나 현재의 기술 수준에 머물면 미래 원전 기술에서는 다른 선진국 내지 중국, 인도 등 신흥국에 그 자리를 양보할 수밖에 없을 것이다. 미래 원자력이란 시대적 요건인 고유 안전성과 지속 가능성을 확보하고 경제성과 함께 핵확산 저항성이 전제되는 원자력 신기술로서 세계와의 경쟁 대상이다. 여기에 핵연료 자원의 유한성에 지속 가능성을 확보하기 위해서 우라늄 효율을 극대화하는 제4세대의 고속로 개발까지 우리나라는 선도적 위치로 가야 한다. 이 기술 개발 역시 출발은 늦었지만 적극적인 개발을 추진하고 있어 소듐고속로의 시현 원자로인 PGSFR을 2028년까지 완성하는 목표를 달성하면, 이를 근간으로 세계 선진국의 경쟁 대열에 나설 수 있다. 정부의 적극적인 지원이 선도적 위치에 갈 수 있는 지름길이다. 고속로 기술 개발과 관련하여 사용후핵연료(SF)의 국가 정책이 아직 확정되지 않아 재활용주기를 전제하고 있는 고속로 개발에 어려움을 주고 있다. 따라서 SF 부지를 2028년까지 확정하는 일정과 함께 국가 SF 정책이 조속히 확정되어야 한다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
• /
• v.9 no.3
• /
• pp.149-159
• /
• 2011

Nuclear power utilities should establish a site-specific groundwater monitoring program for early detection of unplanned radioactive material's releases which can occur due to degradation of systems, structures and components of the nuclear power plants in order to keep the impact of the unplanned releases on the environment and the residents as low as reasonably achievable. For this end, groundwater flow on site should be evaluated based on characterization of the hydrogeology of a site of concern. This paper aims to provide data necessary for establishing groundwater monitoring program which is currently considered at Kori nuclear power plant 1 by characterizing groundwater flow system on the site based on the existing hydrogeological studies and related documents, and by modeling tritium transport. The results showed that the major groundwater flow direction was south-west and that most of groundwater entered a southern and eastern seas. Although the tritium plume also released into the sea, its rate was delayed by dewatering sump.

• 한국지구물리탐사학회:학술대회논문집
• /
• 2005.05a
• /
• pp.87-92
• /
• 2005

The ground-motion (GM) attenuation relations available in Korea has required the validation process for large earthquakes since most of them were developed based on small earthquake database, The Fukuoka earthquake (M=7.0) that occurred near the Korean Peninsula provides invaluable data to indirectly evaluate the attenuation characteristics of the strong GM in Korea. The GM levels (PGA, SA) obtained from the KIK-net downhole stations near the epicenter (R<100km) are reasonably predicted by the GM attenuation relation developed by KEPRI in 2003 for the Kori NPP site, the result of which validates the use of KEPRI GM attenuation relation for predicting GM induced by future large earthquakes. Also, the comparison between the Osaki spectra and response spectra of KIK-net downhole data reveals that the amplitude levels of Osaki spectra are higher than the spectra from KIK-net stations which are believed to be installed at the seismic basement.

• Journal of the Korean Geophysical Society
• /
• v.8 no.3
• /
• pp.109-113
• /
• 2005

The ground-motion (GM) attenuation relations available in Korea has required the validation process for large earthquakes since most of them were developed based on small earthquake database. The Fukuoka earthquake (M=7.0) that occurred near the Korean Peninsula provides invaluable data to indirectly evaluate the attenuation characteristics of the strong GM in Korea. The GM levels (PGA, SA) obtained from the KIK-net downhole stations near the epicenter (R<100km) are reasonably predicted by the GM attenuation relation developed by KEPRI in 2003 for the Kori NPP site, the result of which validates the use of KEPRI GM attenuation relation for predicting GM induced by future large earthquakes. Also, the comparison between the Osaki spectra and response spectra of KIK-net downhole data reveals that the amplitude levels of Osaki spectra are higher than the spectra from KIK-net stations which are believed to be installed at the seismic basement.

• Journal of the KSME
• /
• v.29 no.1
• /
• pp.40-47
• /
• 1989

신형안전로 개발의 필요성을 설비개발이라는 관점에서 우리가 해결해야 할 과제로 요약하면 첫 째는 설계개념이다. 즉 어떠한 설계개념을 채택하여야만 설비의 단순화가 가능하며 중소형이 면서도 경제성 확보가 가능할 것인가 하는 점이며, 둘째는 이러한 새로운 개념은 과연 원전의 안전성이 혁신적으로 개선된 것이며, 어디에나 용이하게 건설이 가능토록 부지요건이 완화된 것이며, 전문가가 아닌 사람도 용이하게 운전가능토록 준 무인운전 수준의 편의성 확보가 가능 한가 하는 점이다. 셋째는 극히 소용량인 지역난방 원자로에서부터 대용량 발전 설비에 이르 기까지의 연계 개발 계획으로서 수요처별 수요 적응 특성 반영과 Modular Type 또는 기타의 방법으로 용이하게 용량을 확장할 수 있는 방법을 강구하는 문제이다.

• Proceedings of the Earthquake Engineering Society of Korea Conference
• /
• 1998.10a
• /
• pp.297-303
• /
• 1998

The uniform hazard spectrum of Wolsong Nuclear Power plant Site is computed in order to estimate probabilistically the characteristics of spectral ground response. The spectral hazard values calculated from the seismic zoning maps proposed by eight seismologist are combined with equal weight to produce a uniform hazard spectrum. The uniform hazardd spectra corresponding to reference probabilities of 1.0 $\times$10-4/year and 1.0$\times$10-5/year are presented, which largely depend on the spectral attenuation relation. The computational results of this study contribute to verify the conservatism of the design ground spectrum of Wolsong Nuclear Power Plant.

• Journal of the Earthquake Engineering Society of Korea
• /
• v.10 no.1 s.47
• /
• pp.63-74
• /
• 2006

The seismic fragility analysis method has been used as a quantitative seismic safety evaluation method for the NPP(Nuclear Power Plant) structures and equipments. The seismic fragility analysis gives a realistic seismic capacity excluding the convertism included in the design stage. The conservatism is considered as the probabilistic parameters related to the response and capacity in the seismic fragility analysis. In this study, the displacement based seismic fragility analysis method was proposed based on the nonlinear dynamic analysis results. In this study, the seismic safety of the prestressed concrete containment building of KSNP(Korean Standard Nuclear Power Plant) was evaluated for the scenario earthquakes, neat-fault, far-fault, design earthquake and probability based scenario earthquake, which can be occurred in the NPP sites.