• Nuclear industry
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• v.33 no.5
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• pp.92-97
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• 2013

소형 모듈 원전 (SMRs, Small Modular Reactors) 시장 선점을 위한 각국의 경쟁이 치열하게 전개되고 있다. 그 중에서도 특히 미국, 러시아, 중국, 한국, 아르헨티나를 포함한 15개 국가가 향후 20년에 걸쳐 펼쳐질 소형 모듈 원전 시장 선점 경쟁에서 치열한 각축전을 벌일 것으로 예상되고 있다.

• Journal of the Korean Society of Marine Environment & Safety
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• v.30 no.5
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• pp.499-505
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• 2024

To address the issue of global warming, various regulations and policies for reducing greenhouse gas emissions are being implemented. In this context, the number of countries targeting carbon neutrality, the latter of which entails reducing net carbon emissions to zero, is increasing, and small modular reactors (SMRs) are investigated extensively as a new model for power plants. SMRs, although measuring only 5%-10% of the size of conventional large nuclear power plants, are highly efficient systems that can generate hundreds of megawatts of power. Compared with fossil fuel-based power plants, SMRs generate less carbon emissions and can complement the unstable energy supply from renewable sources. However, the use of SMRs is opposed by local residents owing to the risk of significant radioactive-material leakage when a nuclear-power-plant accident occurs. Hence, floating, small nuclear-power vessels are being investigated and installed in the ocean, thus simplifying the process of securing land, compensating nearby residents, and increasing safety against natural disasters. In this study, the towing stability of SMR power ships is analyzed, and the result shows no significant risk of towing to the destination in sea states 3, 4, and 5.

• Review of KIISC
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• v.33 no.6
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• pp.15-20
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• 2023

지금까지 원자력 산업은 국가의 전기수요 상당부분을 충족시키기 위해 대형 원전을 중심으로 건설하고 운영해 왔다. 그러나 대형 원전의 안전사고, 사용후 핵연료 처리 문제, 건설비 증가 등으로 세계 원자력 산업은 안전성을 향상시킨 소형모듈원전(Small Modular Reactor, 이하 SMR)의 개발에 주력하고 있다. 이에 본 논문에서는 SMR에 활용이 예상되는 최신기술에 따라 증대되는 사이버보안 이슈와 관련 규제 동향에 관해 기술한다.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05a
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• pp.684-689
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• 1998

전기출력 150 MWe(열출력 392 MWth)의 U-Zr 이원합금핵연료 사용 소형노심인 액채금속로 KALIMER 98.03 설계 노심에 대하여 열수력 특성을 분석하고, 그 결과를 97.07 설계 노심의 열수력 설계특성과 비교.분석하였다. 분석을 위해서 냉각재 유량배분 계산에 ORFCE-F, 유량배분에 따를 온도계산에는 ORFCE-T를 사용하였는데, 이들은 현재 KALIMER 개발의 개념설계 초기 단계에서 사용하고 있는 모듈이다. 열수력 특성 분석은 먼저 각 집합체의 출력과 핵연료봉의 최고 선출력에 따라 유량그룹을 설정하고, 각 집합체의 최고온도 연료봉에 대하여 냉각재 온도, 피복관 중심온도, 핵연료 중심온도 등을 계산하는 방식으로 수행한다 열수력 특성분석 결과 98.03 설계 노심이 97.07 설계 노심에 비해 노심내 출력분포가 더욱 평탄화 되어, 노심 유량영역은 16개에서 11개로 감소되었고, 그에 따를 온도계산에서도 피복관 중심에서의 2$\sigma$ 온도가 6$65^{\circ}C$에서 628$^{\circ}C$로 낮아지는 둥 매우 향상된 설계임을 알 수 있었다.

• Proceedings of the KIPE Conference
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• 2019.07a
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• pp.53-55
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• 2019

리튬 이온 배터리가 소형 모바일 기기, 전기 자동차, 에너지 저장장치 등에 상용화됨에 따라서 이의 충전 상태(SOC) 추정 및 셀, 모듈의 건전성(SOH)의 예측이 배터리 사용 기기의 관리 지표로 사용되고 있다. 리튬 이온 배터리는 여러 차례의 방전으로 노화되어 기기의 요구 부하를 공급가능한지 지표로 평가되어야 한다. 정확한 SOH 추정을 위해 리튬 이온 배터리의 방전 용량 실험이 주기적으로 진행되어야 하며, 이를 통해 오프라인 기반의 SOH 추정이 가능해진다. 본 논문에서는 베이지안 회귀분석 방법을 이용하여 오프라인 SOH 추정을 진행하기 위해 방전 용량을 추정하였으며, 고출력 배터리인 18650 25R셀을 이용하여 방전 용량 추정 결과 방전 전류 1 C-rate에서 1%, 2 C-rate에서 2%의 추정 오차율을 나타냈다.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.20 no.1
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• pp.49-55
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• 2024

Stainless 630 (or 17-4PH) is a precipitation-hardening martensitic stainless steel that has excellent mechanical properties and corrosion resistance. These characteristics make the STS630 to be used as a consisting material for various components such as spider, pin, spring, and spring retainer, of the control rod drive mechanism (CRDM) in pressurized water reactors (PWRs). In general, it is well known that the oxide layer of stainless steel consists of a duplex layer, a compact inner layer of FeCr₂O₄ spinel, and a coarse-grained outer layer of Fe₃O₄ spinel in PWR primary coolant condition. However, the characteristics of the oxide layer can be sensitively influenced by various water chemistry conditions such as temperature, dissolved oxygen, dissolved hydrogen, pH, pH adjuster type, and exposure time. In this work, we investigate the corrosion properties of the STS630 as a function of coolant temperature in an NH3 alkaline solution for its boron-free application in a small modular reactor, to confirm the feasibility for usage as a boron-free SMR structural material. As a result, oxide layer of corroded STS630 is consist of double-layer oxides consisting of a Cr-rich dense inner oxide and a Fe-rich polyhedral outer particles like as that in commercial PWR primary coolant. The corrosion rate of STS630 increases with increase in test time and temperature and the corrosion rate-time model equation was developed based on experimental data. Overall, it is expected that the results in this study provides useful data for the corrosion behavior of STS630 in alkaline environments, contributing to the development of selecting suitable materials for SMRs.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.18 no.2
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• pp.69-76
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• 2022

In order to prepare for a future nuclear market, research for developing floating small modular reactor has been initiated with the aim of differentiating it from large nuclear power plants such as distributed power, heat supply to remote communities and sea water desalination. Depending on the characteristics of the small modular reactor, it is necessary to design a plate and shell heat exchanger that can be manufactured smaller than the U-tube recirculation method. In this study, 12 cases are selected by changing the diameter of the heat plate, the thickness of the device body and the size of the stiffener. Finite element analysis is performed by setting the stress classification lines for the point at which deformation is expected under external pressure conditions for these analysis cases. For the basic design of the plate and shell heat exchanger, the optimal conditions are derived by analyzing the tendency of stress change in the device body and stiffener.

• Journal of the Korean Society for Aeronautical & Space Sciences
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• v.49 no.6
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• pp.473-480
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• 2021

In this paper, We analyze and present improvements to problems in software quality through Static Analysis for Open Source, which is widely used as the Flight Controller software for small unmanned aerial vehicle drones. MISRA coding rules, which are widely applied based on software quality, have been selected. Static analysis tools were used by LDRA tools certified international tools used in all industries, including automobiles, railways, nuclear power and healthcare, as well as aviation. We have identified some safety-threatening problems across the quality of the software, such as structure of open source modules, analysis of usage data, compliance with coding rules, and quality indicators (complexity and testability), and have presented improvements.

• Journal of Radiation Protection and Research
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• v.39 no.3
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• pp.150-158
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• 2014

Radiation-related practitioners and radiation-treated patients at medical institutions are inevitably exposed to radiation for diagnosis and treatment. Although standards for maximum doses are recommended by the International Commission on Radiological Protection (ICPR) and the International Atomic Energy Agency (IAEA), more direct and available measurement and analytical methods are necessary for optimal exposure management for potential exposure subjects such as practitioners and patients. Thus, in this study we developed a system for real-time radiation monitoring at a distance that works with existing portable device. The monitoring system comprises three parts for detection, imaging, and transmission. For miniaturization of the detection part, a scintillation detector was designed based on a silicon photomultiplier (SiPM). The imaging part uses a wireless charge-coupled device (CCD) camera module along with the detection part to transmit a radiation image and measured data through the transmission part using a Bluetooth-enabled portable device. To evaluate the performance of the developed system, diagnostic X-ray generators and sources of $^{137}Cs$, $^{22}Na$, $^{60}Co$, $^{204}Tl$, and $^{90}Sr$ were used. We checked the results for reactivity to gamma, beta, and X-ray radiation and determined that the error range in the response linearity is less than 3% with regard to radiation strength and in the detection accuracy evaluation with regard to measured distance using MCNPX Code. We hope that the results of this study will contribute to cost savings for radiation detection system configuration and to individual exposure management.