• 한국안전학회지
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• 제31권5호
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• pp.177-186
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• 2016

When an event is occurred in a nuclear power plant (NPP), the NPP operator reports it referred by the regulation on reporting and public announcement of accidents and incidents. Some of the events do not need to be reported because they are not included in the reporting criteria of the regulation. However, it is necessary that they should be managed effectively because the accident can be occurred by the recurrence of a lot of them as precursors. Among the events not included in the reporting criteria of the regulation, near miss is the event that is not occurred but can generate a significant consequence. This can provide the cause of the event which does not result an accident. So, it is able to offer insightful knowledges to prevent higher level events about the function and process of NPP. The objective of this study is to analyze the issues of near miss events, prepare the defence against the risk, and improve the management process of NPP. To achieve it, this study performed to analyze the management structure and status of near miss events as well as the accident reporting system of the domestic and foreign regulation bodies. In case of Korea, the status was analyzed by quantitative data, licensee event reports and procedures. Based on these, we could find the causes that near miss events were not managed effectively. Then, systematic alternatives that reflected the perspective of man, technology and organization were drawn.

• Nuclear Engineering and Technology
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• 제35권6호
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• pp.507-514
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• 2003

Recently dry decontamination/surface-cleaning technology using plasma etching has been focused in the nuclear industry. In this study, the applicability of this new dry processing technique are experimentally investigated by examining the etching reaction of $UO_2$, Co, and Mo in r.f. plasma with the etchant gas of $CF_4/O_2$ mixture. $UO_2$ is chosen as a representing material for uranium and TRU (TRans-Uranic) compounds while metallic Co and Mo are selected because they are the principal contaminants in the used metallic nuclear components such as valves and pipes made of stainless steel or inconel. Results show that in all cases maximum etching rate is achieved when the mole fraction of $UO_2\;in\;CF_4/O_2$ mixture gas is $20\%$, regardless of temperature and r.f. power. In case of $UO_2$, the highest etching reaction rate is greater than 1000 monolayers/min. at $370^{\circ}C$ under 150 W r.f. power which is equivalent to $0.4{\mu}m/min$. As for Co, etching reaction begins to take place significantly when the temperature exceeds $350^{\circ}C$. Maximum etching rate achieved at $380^{\circ}C\;is\;0.06{\mu}m/min$. Mo etching reaction takes place vigorously even at relatively low temperature and the reaction rate increases drastically with increasing temperature. Highest etching rate at $380^{\circ}C\;is\;1.9{\mu}m/min$. According to OES (Optical Emission Spectroscopy) and AES (Auger Electron Spectroscopy) analysis, primary reaction seems to be a fluorination reaction, but carbonyl compound formation reaction may assist the dominant reaction, especially in case of Co and Mo. Through this basic study, the feasibility and the applicability of plasma decontamination technique are demonstrated.

• 방사선산업학회지
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• 제5권4호
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• pp.337-345
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• 2011

In order to provide an effective preparedness for a nuclear or radiological emergency happening in the domestic or neighborhood countries and to solve the vague fear of the people for the ingestion of radioactive livestock products, the establishment of national guideline level for radionuclides in feed is urgently necessary. This is because it is important to secure the safety and to manage the crisis in the agricultural, fishery and food sector by performing the effective safety control during and after nuclear incident. This study was performed to investigate the report cases of international organizations and foreign countries to set up a domestic control standard for managing radioactive substances that may be contaminated in animal feeds due to the nuclear power plant incident. In addition, an attempt was made to provide a useful reference that can help prepare a domestic control standard, using a coefficient that can consider the transfer into livestock through the intake of radioactive contaminated animal feeds. The standard radioisotopes investigated were confined to radioactive cesium ($^{137+134}Cs$) and iodine ($^{131}I$). Guideline level for the radionuclides was calculated by using the transfer coefficient factor and the maximum daily intake of animal feed provided by IAEA. For example, the maximum daily intake of animal feed was set as $25kg\;d^{-1}$ for dairy cows, $10kg\;d^{-1}$ for beef cattle, $3.0kg\;d^{-1}$ for pigs and $0.15kg\;d^{-1}$ for chickens. The result values for radioactive cesium were calculated as $8,696Bq\;kg^{-1}$, $4,545Bq\;kg^{-1}$, $1,667Bq\;kg^{-1}$ and $2,469Bq\;kg^{-1}$, respectively. The results for radioactive iodine showed the ranges between $741Bq\;kg^{-1}$ and $76,628Bq\;kg^{-1}$. These data can be utilized as a scientific reference for the preparation of a crisis management manual for the emergency control due to nuclear power plant accident in Korea and neighboring country. These results will contribute to establish the safe feed management system at national level as manual for responding the radioactive exposure of agricultural products and animal feeds, which are currently not established.

• 비파괴검사학회지
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• 제9권1호
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• pp.106-110
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• 1989

Bolting degradation problems in primary coolant pressure boundary applications have become a major concern in the nuclear industry. In the bolts concerned, the failure mechanism was either corrosion wastage(loss of bolt diameter) or stress-corrosion cracking.(3) Here the manual ultrasonic testing of RPV(Reactor Pressure Vessel) and RCP(Reactor Coolant Pump) stud has been performed. But it is difficult to detect indications because examiner can not exactly control the rotation angle and can not distinguish the indication from signals of bolt. In many cases, the critical sizes of damage depth are very small(1-2 mm order). At critical size, the crack tends to propagatecompletly through the bolt under stress, Resulting in total fracture.(3) Automatic stud scanner for studs(bolts) was developed because the precise measurement of bolt diameter is required in this circumstance. By use of this scanner, the rotation angle of probe was exactly controlled and the exposure time of radiations was reduced.

• 한국CDE학회논문집
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• 제17권4호
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• pp.225-233
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• 2012

A comprehensive research effort in order to develop and disseminate modernized Korean housing (Hanok) has recently been initiated by Korean government. This large scale research project encompasses a wide spectrum of housing development including public policy, architectural plans, modules, construction materials and methods, prefabricated assemblies, automated production, construction management, and advanced information systems. For the purpose of integrating and automating the whole processes from an industry perspective, it is of great importance to develop a standard classification system and project numbering system (PNS) for the modernized Korean housing. This paper focuses on the standard classification systems and PNS for cost and schedule control. The distinct characteristics and managerial requirements were explored and embedded into the proposed classifications for modernized Hanok.

• The Journal of the Acoustical Society of Korea
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• 제16권1E호
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• pp.9-14
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• 1997

Check valves used in industrial and Nuclear Power Plant safety systems are susceptible to failure modes generally associated with wear of internal parts. Specifically, hinge pins, disc studs, pistons, and other mechanical parts may degrade over time, and in some cases, may which might produce a disabling event leading to plant or process shutdown. The primary diagnostic technique in the past has been to disassemble the valves. This procedure is costly, time consuming, and in the nuclear industry, it can lead to radiation exposure in some situations. Additionally repair and reassembly of a valve does not ensure proper operation. Non-intrusive diagnostic technologies including acoustics and magnetics with a digital signal analysis allow to evaluate check valve performance without a disassembly and is able to help the user detect degraded valve conditions.

• Nuclear Engineering and Technology
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• 제53권4호
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• pp.1357-1368
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• 2021

This paper presents thermal aging effect on fracture toughness properties of GTAW (gas tungsten arc welding) and SMAW (shielded metal arc welding) of 316L stainless steels, and investigates the applicability of the existing three thermal aging models for CASS (cast stainless steels). Thermal aging was carried out at 350 ℃ for up to 15,000h and at 400 ℃ up to 8,000h. After aging, tensile and fracture toughness tests using 0.5T C(T) specimens were carried out at room temperature and at 288 ℃. Comparing with the predictions using three (ANL, French and H3T) thermal aging models for CASS show that the predictions can be very non-conservative at operating temperature, and thus that the existing thermal aging models for CASS cannot be applied to the welded stainless steels.

• 국제학술발표논문집
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• The 8th International Conference on Construction Engineering and Project Management
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• pp.371-380
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• 2020

With the 4th industrial revolution, many advanced information technologies are being applied to the area of construction engineering and project management. These applications are usually focusing on design, construction and operation stage and are producing many meaningful fruits. Even though these studies are very important for the development of the construction industry, this study insists that the other stage perspective such as construction business also should be emphasized. Because business phase has significant impacts on the success of a construction project as well as design, construction and operation phase. So, this study reviewed the intelligent-approach papers in planning and marketing, estimation and bid, contract and claim, and project financing fields. This study provides some insights such as values, difficulties, limitations and future directions of business intelligence application.

• 에너지공학
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• 제23권2호
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• pp.125-148
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• 2014

본 논문은 기술-제도 복합시스템을 활용하여 우리나라의 전력 산업이 현재의 탄소의존 경로에 이르게 된 다양한 원인들을 역사적으로 분석하고, 우리나라 전력산업이 탄소고착에서 벗어나 지속가능한 체제로 전환할 수 있는 가능성에 대해 평가하였다. 분석의 결과 우리나라 전력산업의 탄소고착을 강화시키는 요인들은 시장, 기업, 소비자, 정부측면에 고르게 분포되어 있는 것으로 드러났다. 경제성에 근거한 대규모 발전설비를 선호하는 정부정책과 저렴한 전기요금제도, 요금 인상을 엄격히 억제하는 물가관리 시스템, 여름철과 겨울철 전력수요 급증, 탄력적인 요금제도의 부재, 유연탄과 천연가스 설비의 확대 등이 그것이다. 반면 원자력발전과 스마트 그리드를 제외하면, 탄소고착을 완화시키는 요인들은 주로 환경관련 법률이나 신재생관련 법률이다. 전력산업의 탄소배출이 전원구성에 의해 가장 큰 영향을 받고, 우리 경제가 제조업 기반의 수출 위주이며, 산업과 상업부문의 전력소비가 총 85% 이상이라는 점 등을 고려할 때, 우리나라 전력산업이 이른 시일 내에 탄소고착에서 벗어날 수 있을 가능성은 그리 높아 보이지 않는다. 따라서 우리나라 전력산업이 탄소고착을 탈피하기 위해서는 시장, 기업, 소비자, 정부 차원에서 복합적인 개선 노력이 필요하다. 우선, 시장측면에서는 주요국처럼 독점을 완화하여 적극적인 신재생에너지 확대와 소비자 선택권을 보장하는 조치가 필요하다. 기업측면에서는 적극적인 수요관리와 신재생을 포함하는 분산전원의 확대가 시급한 과제이다. 소비자측면에서는 탄소고착 완화를 위한 다양한 요금제 도입과 소비자의 의식전환 노력 등이 필요하다. 마지막으로, 정부에서는 수급계획 수립 시 중요하게 고려되지 못했던 다양한 외부 비용들, 예를 들어 환경비용, 사회적 갈등비용 등을 포함하는 제도 개선이 시급히 필요하다.

• 자원ㆍ환경경제연구
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• 제31권4호
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• pp.865-885
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• 2022

2021년, 정부는 국가 온실가스 감축목표(Nationally Determined Contribution, NDC)를 상향 설정하고 에너지 분야의 주요 감축 방안과 감축목표를 제시하였으나, 다양한 쟁점이 논의되고 있다. 그 중 NDC 감축목표를 달성하기 위한 에너지수요와 신재생에너지 발전 비중을 17개 광역시도 통합평가모형 GCAM-Korea로 분석하였다. 그 결과, 2030년 최종소비부분의 에너지수요는 2018년과 비슷한 수준이었다. 이는 석탄 비중의 감소와 전기화가 진행되면서 가능한 것으로 보이며, 특히, 산업부문에서 그 현상이 뚜렷이 나타났다. 최종소비부문에서 증가한 전기수요와 감소한 석탄 발전량(2030년 발전 비중 12.8%)은 신재생(33.1%), 가스(24.6%), 원자력(18.0%)이 부담하는 것으로 나타났다. 이에 따라 미래의 주요 발전지역은 현 주요 발전지역인 충남(주요 발전원, 석탄)에서 경북(원자력), 경기(가스), 전남(원자력, 가스), 강원(태양광, 풍력)으로 바뀌었다. 이와 같은 연구 결과는 국가와 지자체의 에너지 정책 및 온실가스 감축 전략 도출을 위한 기반자료로 활용될 수 있을 것으로 기대한다.