• 원자력산업
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• 제19권6호통권196호
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• pp.36-41
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• 1999

우리 나라의 에너지 안보 정도를 정량화하여 나타낼 수 있는 에너지 안보 지수를 개발, 제시하고 이를 이용하여 원자력 발전의 도입이 국내 에너지 안보에 기여한 정도를 측정하였다. 에너지 안보에의 기여 항목으로는 에너지원 다원화와 에너지 수입의존도를 선정하였으며, 원자력의 도입 여부에 따른 에너지 안보 지수의 변화를 비교함으로써 에너지 안보와 원자력 도입 여부와의 관계를 정량적으로 살펴보았다. 또한 본 연구에서 개발한 에너지 안보 지수를 이용하여 주요국의 안보 지수를 산출함으로써 우리 나라의 에너지 안보의 정도를 외국과 비교하였다. 이러한 분석을 통해 그 동안 정성적으로만 논의되어 왔던 원자력 발전의 에너지 안보에 대한 기여 효과가 보다 명확하게 정량화되어 평가될 수 있었다.

• 한국지진공학회:학술대회논문집
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• 한국지진공학회 1997년도 추계 학술발표회 논문집 Proceedings of EESK Conference-Fall 1997
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• pp.82-89
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• 1997

Due to aging of the imported seismic monitoring system of Uljin 1＆2 units it is difficult for this system to provide enough functions needed for the security of seismic safety and the evaluation of the earthquake data from the seismic instrumentation. For this reason, it is necessary to replace the seismic monitoring system of Uljin 1＆2 units with an upgraded system with corresponding softwars. With operation of this system which incorporates the man-machine interface technology, the operators in nuclear power plant can rapidly and correctly determine the exceedance of Operating Basis Earthquake.

• 정보보호학회논문지
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• 제26권3호
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• pp.769-776
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• 2016

최근 사이버공격은 국경을 초월하여 국가의 사이버 공간을 지속적으로 위협하고 있다. 이런 사이버공격은 국가 주요기반시설을 마비시킬 수 있는 수준으로 지능화 고도화되는 양상을 보여주고 있다. 이런 사실은 원전 해킹 위협, 3.20 사이버테러 등의 사건에서 잘 볼 수 있다. 특히 국가 중요 정보가 존재하는 국가 공공기관에서는 이와 같은 사이버공격으로 대규모 피해가 예상되기 때문에 사전예방이 중요하다. 기술적인 대응도 중요하지만 국가 공공기관 근무자에게 사이버보안 교육을 통해 사이버 보안의식 고취 및 보안 전문지식 향상을 통해 보안 수준을 높이는 것이 중요하다. 이에 본 논문에서는 공공분야 근무자들에 대한 단기 교육과정을 통해 최고의 보안 효과 상승을 위한 교육과정을 제안한다.

• Nuclear Engineering and Technology
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• 제49권2호
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• pp.335-341
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• 2017

The main control room (MCR) in advanced nuclear power plants (NPPs) has changed from analog to digital control system (DCS). Operation and control have become more automated, centralized, and accurate due to the digitalization of NPPs, which has improved the efficiency and security of the system. New issues associated with human reliability inevitably arise due to the adoption of new accident procedures and digitalization of main control rooms in NPPs. The LingAo II NPP is the first digital NPP in China to apply the state-oriented procedure. In order to address issues related to human reliability analysis for DCS and DCS + state-oriented procedure, the Hunan Institute of Technology conducted a research project based on a cooperative agreement with the LingDong Nuclear Power Co. Ltd. This paper is a brief introduction to the project.

• Nuclear Engineering and Technology
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• 제55권9호
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• pp.3506-3513
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• 2023

In this paper, we demonstrate the neutron attenuation of dry cask shielding materials using the S670e helium-4 detector manufactured by Arktis Radiation Ltd. In particular, two materials expected to be applied to the TN-32 dry cask manufactured by ORANO Korea and KORAD-21 by the Korea Radioactive Waste Agency (KORAD) were utilized. The measured neutron attenuation was compared with our Monte Carlo N-Particle Transport simulation results, and the difference is given as the root mean square (RMS). For the fast neutron case, a rapid decline in neutron counts was observed as a function of increasing material thickness, exhibiting an exponential relationship. The discrepancy between the experimentally acquired data and simulation results for the fast neutron was maintained within a 2.3% RMS. In contrast, the observed thermal neutron count demonstrated an initial rise, attained a maximum value, and exhibited an exponential decline as a function of increasing thickness. In particular, the discrepancy between the measured and simulated peak locations for thermal neutrons displayed an RMS deviation of approximately 17.3-22.4%. Finally, the results suggest that a minimum thickness of 5 cm for Li-6 is necessary to achieve a sufficiently significant cross-section, effectively capturing incoming thermal neutrons within the dry cask.

• Journal of Radiation Protection and Research
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• 제48권1호
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• pp.52-57
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• 2023

Background: Korea Atomic Energy Research Institute (KAERI) operates several nuclear research facilities licensed by Nuclear Safety and Security Commission (NSSC). The emergency preparedness requirements, GSR Part 7, by International Atomic Energy Agency (IAEA) request protection strategy based on the hazard assessment that is not applied in Korea. Materials and Methods: In developing the protection strategy, it is important to consider an accident scenario and its consequence. KAERI has tried the hazard assessment based on a hypothesis accident scenario for the major nuclear facilities. During the assessment, the safety analysis report of the related facilities was reviewed, the simulation using MELCOR, MACCS2 code was implemented based on a considered accident scenario of each facility, and the international guidance was considered. Results and Discussion: The results of the optimized protective actions were 300 m evacuation and 800 m sheltering for the High-Flux Advanced Neutron Application Reactor (HANARO), the evacuation to radius 50 m, the sheltering 400 m for post-irradiation examination facility (PIEF), 100 m evacuation or sheltering for HANARO fuel fabrication plant (HFFP) facility. Conclusion: The results of the optimized protective actions and its distances for the KAERI facilities for the maximum postulated accidents were considered in establishing the emergency plan and procedures and implementing an emergency exercise for the KAERI facilities.

• Nuclear Engineering and Technology
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• 제55권10호
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• pp.3525-3534
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• 2023

Non-uniformity of Pu and Cm composition in used nuclear fuel was analyzed to determine its effect on Pu accountancy in pyroprocessing, while employing the Pu-to-²⁴⁴Cm ratio method. Burnup simulation of a typical pressurized water reactor fuel assembly, required for the analysis, was carried out using MCNP code. Used fuel nuclide composition, as a function of nine axial and two radial meshes, were evaluated. The axial variation of neutron flux and self-shielding effects were found to affect the uniformity of Pu and Cm compositions and in turn the Pu-to-²⁴⁴Cm ratio. However, the results of the study showed that these non-uniformities do not affect the use of Pu-to-²⁴⁴Cm ratio method for Pu accountancy, if the measurement samples are drawn from the voloxidized powder at the feed step of pyroprocessing. 'Material Unaccounted For' and its uncertainty estimates are also presented for a pyrprocessing facility to verify safeguards monitoring requirements of the IAEA.

• Nuclear Engineering and Technology
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• 제35권3호
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• pp.243-250
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• 2003

Nuclear power plants (NPPs) will be highly connected network enabled systems in the future. Using the network and web enabled tools, NPPs will be remotely monitored by operators at any time from any place connected to the network via a general web browser. However, there will be two major issues associated with this implementation. The first is the security issue. Only the authorized persons need to be allowed to access the plant since NPP is a safety-critical system. However, the web technology is open to the public. The second is the network disturbance issue. If operators can not access the plant due to network disturbances, the plant will come into the out-of-control situation. Therefore, in this work, we performed a conceptual design of a web-based remote monitoring and control system (RMCS) considering these issues.

• 한국건축시공학회:학술대회논문집
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• 한국건축시공학회 2013년도 춘계 학술논문 발표대회
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• pp.268-270
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• 2013

The construction project can be defined as a network combined between elements which are engineering, procurement, construction, start-up, and has a plenty of subjects and partners. For the successful project management in construction industry, it is necessary to adopt various management methods, such as lean production, information network system, SCM(Supply Chain Management), which can increase the efficiency of project management. During recent years, even though various management techniques have been applied, the SCM system has not formulated in construction industry. Especially, the Nuclear Power Plant Construction which requires high regulations of the safety and security has not applied SCM. Therefore, this study aimed to propose technology area of SCM in Korean Nuclear Power Plant Construction.

• 한국전자통신학회논문지
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• 제6권6호
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• pp.839-847
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• 2011

원자력발전소의 계측제어계통은 제어, 감시기능을 수행하여 안전운전을 위한 두뇌 역할을 하는 핵심적인 분야이다. 최근 계측제어계통은 마이크로프로세서기반의 디지털 기술을 받아들여 디지털화되었다. 그러나 계측제어계통의 디지털시스템은 아날로그 기반 시스템에 비해 사이버위협에 매우 취약하여, 사이버공격에 의해 발전소 안전에 부정적인 영향을 받을 수 있다. 따라서 사이버침해에 대응할 수 있는 사이버 보안 대책이 계측제어계통에 요구된다. 사이버 보안성이 우수한 계통 설계를 위해서는 계측제어계통을 구성하는 자산에 대한 효과적인 자산분석이 요구된다. 본 연구에서는 원자로 계측제어설계의 사이버보안 적합성을 분석하기 위한 전 단계로 계측제어계통의 디지털 자산을 분석하기 위한 방법론을 제안한다. 제안된 디지털자산 분석 방법은 자산식별, 식별된 자산에 대한 평가방법으로 구성된다. 제안된 자산분석방법은 원자력발전소 계측제어계통의 사이버보안을 위한 자산분석에 응용하였다.