• 방사성폐기물학회지
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• 제15권4호
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• pp.391-402
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• 2017

한국원자력환경공단에서는 국내 경수로 원전에서 발생된 사용후핵연료를 건식으로 저장할 수 있는 콘크리트 용기를 개발하였다. 본 저장용기는 사용후핵연료가 건식환경에서 장기간 저장되는 동안 용기 및 사용후핵연료의 건전성이 유지되며, 방사선량률이 저장시설의 설계기준을 초과하지 않도록 설계되어야 한다. 특히, 저장시설은 정상 및 사고조건에서 적절한 방사선 방호를 위한 차폐설계가 이루어져야 한다. 이를 위해 본 연구에서는 미국 10CFR72 및 10CFR20의 기술기준과 NRC의 표준 심사지침 NUREG-1536에서 제시한 평가방법에 따라 건식저장조건하에서 단일 콘크리트용기 및 $2{\times}10$ 용기배열조건의 선량율을 평가하였다. 평가결과, 일반인에 대한 연간선량 한도인 0.25 mSv를 만족하는 통제구역 경계까지의 거리는 약 230 m로 도출되었다. 콘크리트 저장용기의 설계사고는 $2{\times}10$ 배열의 저장시설에서 한 개의 저장용기가 이송 중 전도사고가 발생하여 용기의 바닥면이 통제구역 경계로 향하는 상황으로 가정하였다. 전도된 저장용기의 바닥면으로 부터 100 m 및 230 m 지점에서 각각 12.81 mSv 및 1.28 mSv로 평가되었다. 본 연구를 통해 건식저장조건에서 콘크리트 저장용기 및 저장시설은 적절하게 평가된 통제구역경계까지의 거리가 확보된다면 방사선적 안전성이 유지됨을 확인할 수 있었다. 본 평가결과만으로 건식환경의 저장용기(시설) 설계에 직접 적용하기는 어렵겠으나, 향후 '국가 고준위폐기물 관리 전략'에 근거한 원전내 저장시설 또는 중간저장 시설의 설계 및 운영에 유용한 자료가 될 것으로 사료된다.

• 한국압력기기공학회 논문집
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• 제7권4호
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• pp.12-18
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• 2011

The renewed global interest in nuclear power has arisen from the need to reduce greenhouse gas emissions and to provide sufficient electricity for a growing global population. Many countries with nuclear power plants (NPPs) are still implementing license extensions of 10~20 years, and even consideration is being given to the concept of life-beyond-60, a further period of license extension from 60 to 80 years. To solve the materials aging problem is integral to its success. A foundation for effective aging management of nuclear power plants is that aging is properly taken into account at each stage of a plant's lifetime, i.e. in design, manufacture, construction and operation including long term operation and decommissioning. To evaluate the plant aging phenomena, a lot of background information such as materials and environment of the parts of the reactor and plant systems is needed by the experts. Information on degradation mechanisms is also used. In this paper, a regulation on the integrated materials aging management for nuclear facilities is proposed. The proposed regulation identifies key elements of effective aging management for nuclear power plants and provides the requirements on aging management for nuclear facilities throughout all stages of the lifetime of the plant.

• Nuclear Engineering and Technology
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• 제54권6호
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• pp.2135-2146
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• 2022

A nuclear energy facility is one of the most critical facilities to be safely protected during and after operation because the physical destruction of its barriers by an external attack could release radioactivity into the environment and can cause harmful effects. The barrier walls of nuclear energy facilities should be sufficiently robust to protect essential facilities from external attack or sabotage. Physical protection system (PPS) vulnerability assessment of a typical small nuclear research reactor was carried out by simulating an external attack with a tri-nitro toluene (TNT) shaped charge and results are presented. The reinforced concrete (RC) barrier wall of the research reactor located at a distance of 50 m from a TNT-shaped charge was the target of external attack. For the purpose of the impact assessment of the RC barrier wall, a finite element method (FEM) is utilized to simulate the destruction condition. The study results showed that a hole-size of diameter 342 mm at the front side and 364 mm at the back side was created on the RC barrier wall as a result of a 143.35 kg TNT-shaped charge. This aperture would be large enough to let at least one person can pass through at a time. For the purpose of the PPS vulnerability assessment, an Estimate of Adversary Sequence Interruption (EASI) model was used, which enabled the determination of most vulnerable path to the target with a probability of interruption equal to 0.43. The study showed that the RC barrier wall is vulnerable to a TNT-shaped charge impact, which could in turn reduce the effectiveness of the PPS.

• 한국압력기기공학회 논문집
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• 제19권2호
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• pp.84-92
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• 2023

As temporary storage facilities for spent nuclear fuels in domestic nuclear power plants are expected to be saturated, external intermediate storage facilities would be required in the future. Spent nuclear fuels are stored in metal canisters and then placed in a dry environment within concrete or metal casing for operation. In the United States, the dry storage method for spent nuclear fuels has been operated for an extended period. Based on the corrosion experiences of dry storage canisters in chloride environments, numerous studies have been conducted to reduce corrosion in welds. With the construction of intermediate storage facilities in Korea for spent nuclear fuels expected near coastal areas adjacent to nuclear power plants, there is a need for research on the corrosion occurrence of welds and mitigation methods for canisters in chloride environments. In this paper, we measured and compared the residual stresses in the Heat-Affected Zones (HAZ) after electron beam welding (EBW) and gas tungsten arc welding (GTAW) processes for candidate materials such as 304L, 316L, and duplex stainless steel(DSS). We investigated the possibility of microstructure control through the application of surface modification processes using friction stir processing (FSP). Corrosion tests on each welded specimen revealed a higher corrosion rate in EBW welds compared to GTAW. Furthermore, it was confirmed that corrosion resistance improved due to phase refinement and redistribution of precipitates when FSP was applied.

• 한국지능시스템학회:학술대회논문집
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• 한국퍼지및지능시스템학회 1993년도 Fifth International Fuzzy Systems Association World Congress 93
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• pp.1066-1069
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• 1993

The presence of older installations, in particular nuclear facilities, demands extra studies concerning the safety evaluation of those installations. One of the aspects to deal with is the safety of the several transmission lines in a nuclear installation, for instance the safety of control, safety against fire, etc.. . This paper investigates the use of fuzzy set theory in the inspection of transmission lines of nuclear installations at SCK/CEN, Belgium.

• 제어로봇시스템학회:학술대회논문집
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• 제어로봇시스템학회 1989년도 한국자동제어학술회의논문집; Seoul, Korea; 27-28 Oct. 1989
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• pp.230-234
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• 1989

This paper presents the design of a prototype robot and architecture of a distributed control system. The robot, named as KAEROT, has been developed for the purpose of the reduction of personal radiation exposure and the remote maintenance tasks in nuclear facilities. The mobile system with robotic manipulator has been designed to go up and down stairs. For the dextrous handling, this manipulator will be designed as a redundant type to act like a human arm. Manipulator control system is to be extended easily for further usage with a modular architecture to get independency and reliability by minimizing EMI effects.

• 제어로봇시스템학회:학술대회논문집
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• 제어로봇시스템학회 1990년도 한국자동제어학술회의논문집(국내학술편); KOEX, Seoul; 26-27 Oct. 1990
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• pp.731-735
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• 1990

The mobile robot, named as KAEROT, is designed to go up and down stairs in nuclear facilities. To get a proper stable motion, kinematic modeling and analysis are seriously considered and new climbing algorithm is proposed focused on the stability. A couple of small wheels of one planetary wheel have to contact the surface ol stairs all the time to give the guarantee for stability and safety. To confirm the validity of the proposed algorithm, simulation is carried out. The results make evident of feasibility for the algorithm.

• 한국지하수토양환경학회지:지하수토양환경
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• 제22권3호
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• pp.1-9
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• 2017

The numerical analysis of groundwater flow is indispensable for predicting problems associated with water resource development, civil works, environmental hazards, and nuclear power plant construction. Korea lacks public regulatory procedures and guidelines for groundwater flow modeling, especially in nuclear facility sites, which makes adequate evaluation difficult. Feasible step-by-step guidelines are also unavailable. Consequently, reports on groundwater flow modeling have low-grade quality and often present controversial opinions. Additionally, without public guidelines, maintaining consistency in reviewing reports and enforcing laws is more challenging. In this study, the guidelines for groundwater flow modeling were reviewed for three countries - the United States (Documenting Groundwater Modeling at Sites Contaminated with Radioactive Substances), Canada (Guidelines for Groundwater Modelling to Assess Impacts of Proposed Natural Resource Development Activities), and Australia (Australian Groundwater Modelling Guidelines), with the aim of developing groundwater flow modeling regulatory guidelines that can be applied to nuclear facilities in Korea, in accordance with the Groundwater Act, Environmental Impact Assessment Act, and the Nuclear Safety Act.

• 한국정보통신학회:학술대회논문집
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• 한국정보통신학회 2015년도 춘계학술대회
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• pp.264-266
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• 2015

최근 원자력발전소를 대상으로 하는 사이버위협이 급증함에 따라 원자력사업자는 원자력시설의 컴퓨터 및 정보시스템이 사이버공격에 대해 적절히 보호됨을 보장하여야하며 특히 사이버공격에 노출될 경우 핵물질 불법이전 및 공공안전에 악영향을 끼칠 수 있는 필수 계통에 대한 보호가 필요하다. 본 논문에서는 이를 위해 원자력발전소를 대상으로 하는 사이버위협 현황을 조사하고, 원자력 시설의 필수 계통과 그에 포함된 필수디지털자산들을 식별 방법과 그에 따른 사이버보안 조치를 수행하는 국내 외의 국내 원자력 시설에 적합한 필수 계통 식별 및 보안조치 방법을 분석한다.

• Nuclear Engineering and Technology
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• 제41권5호
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• pp.739-746
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• 2009

This paper introduces facility operation modeling and simulation based primarily on a discrete event system modeling scheme. Many modern industrial facilities are so complex that their operational status cannot be estimated by simple calculations. In general, a facility can consist of many processes and transfers of material between processes that may be modeled as a discrete event system. This paper introduces the current status of studies on operation modeling and simulation for typical nuclear facilities, along with some examples. In addition, this paper provides insights about how a discrete event system can be applied to a model for a nuclear facility. A headend facility is chosen for operation modeling and the simulation, and detailed procedure is thoroughly described from modeling to an analysis of discrete event results. These kinds of modeling and simulation are very important because they can contribute to facility design and operation in terms of prediction of system behavior, quantification of facility capacity, bottleneck identification and efficient operation scheduling.