• 정보보호학회논문지
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• 제29권6호
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• pp.1425-1435
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• 2019

디지털 제어기 적용의 확대로 원자력 시설에 대한 사이버보안 이슈가 대두되었다. 이에 대처하기 위해 공표된 국내 원자력 시설에 대한 사이버보안 기술기준 RS-015에서는 원자력 시스템 개발자에게 보안 기능의 적용과 아울러 알려진 취약점 분석, 보안 기능에 대한 시험 및 평가를 요구하고 있다. 이를 위해서는 원자력 사이버보안 기술기준에 따른 보안 기능 적합성 시험 절차 및 방법 개발이 필요하다. 본 연구에서는 RS-015의 기술적, 운영적, 관리적 보안조치에 대한 세부항목을 분류하여 기기 수준에서 요구되는 보안 요건을 도출하고 기기에 구현되는 보안 기능이 보안 요건을 만족하는지를 시험하는 절차와 방법을 개발하였다. 본 논문에서는 보안 기능 적합성 시험 절차 및 방법 개발을 위한 과정을 설명하고 개발된 시험사례를 제시한다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 춘계학술발표회
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• pp.469-470
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• 2005

• 방사성폐기물학회지
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• 제20권1호
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• pp.65-98
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• 2022

The nuclear legacy that remains in the United Kingdom (UK) is complex and diverse. Consisting of legacy ponds and silos, redundant reprocessing plants, research facilities, and non-standard or one-off reactor designs, the clean-up of this legacy is under the stewardship of the Nuclear Decommissioning Authority (NDA). Through a mix of prompt and delayed decommissioning strategies, the NDA has made great strides in dealing with the UK's nuclear legacy. Fuel debris and sludge removal from the legacy ponds and silos situated at Sellafield, as part of a prompt decommissioning strategy for the site, has enabled intolerable risks to be brought under control. Reactor defueling and waste retrievals across the Magnox fleet is enabling their transition to a period of care and maintenance; accelerated through the adopted 'Lead and Learn' approach. Bespoke decommissioning methods implemented by the NDA have also enabled the relevant site licence companies to tackle non-standard reactor designs and one-off wastes. Such approaches have potential to influence and shape nuclear decommissioning decision making activities globally, including in Korea.

• 한국지진공학회논문집
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• 제20권5호
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• pp.341-349
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• 2016

Currently, researches are being actively conducted in assessing seismic performance of nuclear facilities in USA and Europe. In particular, applying this technique of assessing seismic performance to design of isolation systems in nuclear power plants is being performed and then ASCE 4 Draft (2013) is being revised accordingly in the United States. In order to satisfy the probabilistic performance objectives described by seismic responses with certain confidence levels (ASCE 43, 2005), the probability distributions of these responses have to be defined. What is the minimum number of input ground-motions to obtain the probability distribution precise enough to represent the unknown actual distribution? Theoretical basis, for how to determine the minimum number of input ground-motions for given a logarithmic standard deviation to approximate the unknown actual median of the log-normal distribution within a range of error at a certain level of confidence, is introduced by Huang et al. (2008). However, the relationship between the level of confidence and the range of error is not stated in the previous study. In this paper, based on careful reviews on the previous work, the relationship between the level of confidence and the range of error is logically and explicitly stated. Furthermore, this relationship is also applied to derive the minimum number of input ground-motions in order to approximate the unknown actual logarithmic standard deviation. Several recommendations are made for determining the minimum number of input ground-motions in probabilistic assessment on seismic performance of facilities in nuclear power plants.

• Nuclear Engineering and Technology
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• 제41권4호
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• pp.391-402
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• 2009

This paper introduces the development of safety assessment technology in Korea, focusing on the activities of the Korea Atomic Energy Research Institute in the areas of system thermal hydraulics, severe accidents and probabilistic safety assessment. In the 1970s and 1980s, safety analysis codes and methodologies were introduced from the United States, France, Canada and other developed countries along with technology related to the construction and operation of nuclear power plants. The main focus was on understanding and utilizing computer codes that were sourced from abroad up to the early 1990s, when efforts to develop domestic safety analysis codes and methodologies became active. Remarkable achievements have been made over the last 15 years in the development and application of safety analysis technologies. In addition, significant experimental work has been performed to verify the safety characteristics of reactors and fuels as well as to support the development and validation of analysis methods.

• 한국지리정보학회지
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• 제22권4호
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• pp.131-145
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• 2019

우리나라는 원자력재난 발생 시 인근에 거주하는 주민들을 보호하기 위해 「원자력시설 등의 방호 및 방사능 방재 대책법」에서 방사선비상계획구역을 설정하고 있다. 그러나 방사능사고에 대한 전반적인 관심이 부족하여 원자력 대피시설의 적합성과 관련된 연구는 활발히 이루어지지 않는 것으로 파악된다. 따라서, 본 연구는 취약인구 분포 및 접근성 분석을 기반으로 현재 부산시 방사선 비상계획구역 중 긴급보호조치계획구역의 대피시설의 입지 적정성을 분석하고자 하였다. 분석 결과, 현재 원전시설이 입지하고 있어 가장 위험성이 큰 기장군은 전체 도시지역 면적의 4.05% 만이 5분 내 대피가능지역으로 분석되었으며, 금정구는 36.93%, 해운대구는 37.23% 만이 대피시설 서비스 가능지역에 포함되어 해당 지역에 더 많은 대피시설이 필요한 것으로 보인다. 또한, 노인 인구 집중지역에서 대피시설이 부족한 곳이 많았고, 같은 구내에서도 동 간 격차가 커, 취약계층뿐 아니라 지역 간 형평성을 모두 고려하여 긴급보호조치계획구역 내 대피시설 입지 우선순위를 결정할 필요가 있는 것으로 나타났다.

• 시스템엔지니어링학술지
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• 제17권1호
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• pp.65-75
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• 2021

When the decommissioning of South Korea nuclear power plants is promoted in earnest with the permanent shutdown of Kori Unit 1 in 2017, a large amount of various types of radioactive waste will be generated. For minimal generation and safe management of decommissioning waste, the waste should be made by appropriate classification of the dismantling waste characteristics in accordance with physical, chemical and radiological characteristics to meet the acceptance criteria of disposal facilities. Replacing the preliminary inspection at the site for the compliance of the waste acceptance criteria (WAC) of medium and low-level radioactive waste with the generator's own radioactive waste certification program (WCP), from the perspective of disposal, the optimization of waste management at the national level contributes to the efficient availability of disposal, such as the processing of non-conforming radioactive wastes at the site. To this end, it is important to evaluate radioactivity in each system and area such as nuclear reactors before decommissioning is carried out in earnest, and the prior removal of harmful wastes is important. From waste collection to waste disposal, decommissioning waste should be managed at each stage in consideration of the acceptance criteria of disposal facilities to minimize the generation of non-conforming waste.

• Nuclear Engineering and Technology
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• 제40권5호
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• pp.349-364
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• 2008

Over the years, probabilistic risk assessment (PRA) research activities conducted at the U.S. Nuclear Regulatory Commission (NRC) have played an essential role in support of the agency's move towards risk-informed regulation. These research activities have provided the technical basis for NRC's regulatory activities in key areas; provided PRA methods, tools, and data enabling the agency to meet future challenges; supported the implementation of NRC's 1995 PRA Policy Statement by assessing key sources of risk; and supported the development of necessary technical and human resources supporting NRC's risk-informed activities. PRA research aimed at improving the NRC's understanding of risk can positively affect the agency's regulatory activities, as evidenced by three case studies involving research on fire PRA, human reliability analysis (HRA), and pressurized thermal shock (PTS) PRA. These case studies also show that such research can take a considerable amount of time, and that the incorporation of research results into regulatory practice can take even longer. The need for sustained effort and appropriate lead time is an important consideration in the development of a PRA research program aimed at helping the agency address key sources of risk for current and potential future facilities.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 추계학술발표회
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• pp.939-940
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• 2005

• 한국안전학회지
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• 제35권5호
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• pp.115-120
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• 2020

From 2009 when the CNS facility was installed, the number of reactor failures due to abnormal CNS facility system has increased significantly. Of the total of 19 nuclear reactor shutdowns over the six years from 2009 to 2019, there were 10 nuclear reactor shutdowns associated with the CNS facility, which are very numerous. Therefore, this report intends to analyze the history of nuclear reactor shutdowns due to CNS facility system failure in detail, and to present the root cause and solution to problems. As a result of FMEA implementation of CNS facility system, a total of 76 SPVs were selected. In addition, 10 cases of reactor shutdown history due to CNS facility system abnormalities were analyzed in detailed, and improvement plans for solving the root cause and problem were suggested for each trip history. The results of this study are expected to be able to operate the domestic research reactor and CNS facilities more stably by providing effective measures to prevent recurrence of CNS facilities and reactor trips.