• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2001년도 춘계학술발표회요약집
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• pp.102.2-102
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• 2001

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 춘계학술발표회
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• pp.1267-1268
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• 2005

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2002년도 추계학술발표회요약집
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• pp.100.2-100
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• 2002

• Nuclear Engineering and Technology
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• 제53권9호
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• pp.3085-3099
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• 2021

Investigations of large commercial aircraft impact effect on nuclear power plant (NPP) buildings have been drawing extensive attentions, particularly after the 9/11 event, and this paper aims to numerically assess the damage and vibrations of NPP buildings subjected to aircrafts crash. In Part I of present paper, two shots of reduce-scaled model test of aircraft impact on NPP were conducted based on the large rocket sled loading test platform. In the present part, the numerical simulations of both scaled and prototype aircraft impact on NPP buildings are further performed by adopting the commercial program LS-DYNA. Firstly, the refined finite element (FE) models of both scaled aircraft and NPP models in Part I are established, and the model impact test is numerically simulated. The validities of the adopted numerical algorithm, constitutive model and the corresponding parameters are verified based on the experimental NPP model damages and accelerations. Then, the refined simulations of prototype A380 aircraft impact on a hypothetical NPP building are further carried out. It indicates that the NPP building can totally withstand the impact of A380 at a velocity of 150 m/s, while the accompanied intensive vibrations may still lead to different levels of damage on the nuclear related equipment. Referring to the guideline NEI07-13, a maximum acceleration contour is plotted and the shock damage propagation distances under aircraft impact are assessed, which indicates that the nuclear equipment located within 11.5 m from the impact point may endure malfunction. Finally, by respectively considering the rigid and deformable impacts mainly induced by aircraft engine and fuselage, an improved Riera function is proposed to predict the impact force of aircraft A380.

• 한국산업정보학회논문지
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• 제28권6호
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• pp.1-10
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• 2023

원전 계측제어계통은 정상운전 시 자가 진단기능의 유지보수를 위해 일정 주기로 건전성을 확인하고 있으며, 계획예방정비 기간 동안 기능 및 성능점검을 실시하여 필요한 경우 유지보수를 하고 있다. 하지만 원전의 정보를 계측하고 제어하는 계측제어계통에서도 선제적으로 고장을 진단하고 대처하여 사고전파를 방지할 수 있는 기술개발이 필요하다. 이에 본 논문에서는 계측제어 장비의 환경조건과 자가 진단 데이터를 활용한 신뢰도 함수 추정 방안을 연구하였으며, 고장데이터의 획득을 위해 계측제어 장비의 부품에 대한 Feature 별 확률분포를 가정하여 가상 고장데이터를 생산하였다. 이러한 고장데이터를 바탕으로 생존분석에서 활용되는 대표적인 인공지능 모델(DeepSurve, DeepHit)을 이용하여 신뢰도 함수를 추정하였고, 그와 동시에 전통적인 준모수적 방법론인 Cox 회귀모델을 통해 신뢰도 함수를 추정하여 환경조건과 진단 데이터를 바탕으로 한 잔여 수명 계산을 통해 적용 가능성을 확인하였다.

• 전력전자학회:학술대회논문집
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• 전력전자학회 2005년도 전력전자학술대회 논문집
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• pp.581-583
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• 2005

The paper is final report for speed control upgrade and analysis report which recently performed on PWR NPP safety related EDG KHNP Ulchin NPP No.2 Unit. The upgraded system includes more beneficial function like as 'Slow start with starting ramp', 'Generator load sensing & control capability' and 'Emergency ramp during slow start'. This paper shows functional operation of slow start regime according to NRC regulatory guide which guide regulation to NPP safety related environment.

• 시스템엔지니어링학술지
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• 제9권1호
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• pp.55-63
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• 2013

Nuclear power plant site selection is a complex process and its successful completion is a critical milestone in the NPP development cycle. Proper siting of NPP will ensure public health and safety, environmental conservation, reduced project failure risks and a smooth NPP development process among other benefits. The objective of this paper is to demonstrate the application of systems engineering to the problem of NPP siting in Kenya. The siting process demonstrated in this paper includes stakeholder need analysis where stakeholders are identified and their needs concerning NPP site are elicited and converted into system functional requirements. A value model is then developed and potential sites iteratively subjected to three types of criteria i.e. exclusionary criteria, avoidance criteria and suitability criteria. This process is used to identify the candidate sites. An additive value model; multiple objectives Decision Analysis (MODA) is then used to calculate candidate solutions values. The site with the highest solution value score is selected. Sensitivity studies using different criterion weight sets (thereby reflecting different viewpoints) can be conducted to assess their effect on the selection of a preferred site and thereby lend additional credibility to the decision process.

• 정보처리학회 논문지
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• 제13권5호
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• pp.227-235
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• 2024

원자력발전소에서 디지털 계측제어 시스템 비중이 높아지면서 원자력발전소에 대한 확률론적 안정성 평가 시 소프트웨어에 대한 신뢰도 평가가 중요해졌다. 원전 소프트웨어 신뢰도 추정을 위한 방법들이 몇 가지 제안 되었지만 해당 방법의 효과적 적용을 지원하는 도구 지원이 미비하였다. 본 연구에서는 소프트웨어 개발 품질 및 검증 품질과 같은 정성적 정보와 통계적 시험 결과와 같은 정량적 정보를 활용하여 원전 소프트웨어 신뢰도를 정량적으로 측정할 수 있는 자동화 도구를 설계하였고 구현하였다. 개발된 도구를 산업용 원자로 보호 시스템 사례에 적용한 결과, 개발된 도구가 원전 소프트웨어의 신뢰성 평가를 효과적으로 지원할 수 있음을 확인하였다.

• Nuclear Engineering and Technology
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• 제53권9호
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• pp.3068-3084
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• 2021

Investigations of large commercial aircraft impact effect on nuclear power plant (NPP) buildings have been drawing extensive attentions, particularly after the 9/11 event, and this paper aims to experimentally assess the damage and vibrations of NPP buildings subjected to aircraft crash. In present Part I, two shots of reduce-scaled model test of aircraft impacting on NPP building were carried out. Firstly, the 1:15 aircraft model (weighs 135 kg) and RC NPP model (weighs about 70 t) are designed and prepared. Then, based on the large rocket sled loading test platform, the aircraft models were accelerated to impact perpendicularly on the two sides of NPP model, i.e., containment and auxiliary buildings, with a velocity of about 170 m/s. The strain-time histories of rebars within the impact area and acceleration-time histories of each floor of NPP model are derived from the pre-arranged twenty-one strain gauges and twenty tri-axial accelerometers, and the whole impact processes were recorded by three high-speed cameras. The local penetration and perforation failure modes occurred respectively in the collision scenarios of containment and auxiliary buildings, and some suggestions for the NPP design are given. The maximum acceleration in the 1:15 scaled tests is 1785.73 g, and thus the corresponding maximum resultant acceleration in a prototype impact might be about 119 g, which poses a potential threat to the nuclear equipment. Furthermore, it was found that the nonlinear decrease of vibrations along the height was well reflected by the variations of both the maximum resultant vibrations and Cumulative Absolute Velocity (CAV). The present experimental work on the damage and dynamic responses of NPP structure under aircraft impact is firstly presented, which could provide a benchmark basis for further safety assessments of prototype NPP structure as well as inner systems and components against aircraft crash.

• Nuclear Engineering and Technology
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• 제53권10호
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• pp.3319-3326
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• 2021

As a form of industrial control systems (ICS), nuclear instrumentation and control (I&C) systems have been digitalized increasingly. This has raised in turn cyber security concerns. Cyber security for ICS is important because cyber-attacks against ICS can cause not only equipment damage and loss of production but also personal and public safety hazards unlike in general IT environments. Numerous risk analyses have been carried out to enhance the safety of ICS and recently, many studies related to the cyber security of ICS are being conducted. Many existing risk analyses and cyber security studies have considered safety and cyber security separately. However, both safety and cyber security perspectives should be considered when analyzing risks for complex and critical ICS facilities such as nuclear power plants (NPPs). In this paper, the STPA-SafeSec methodology is selected to consider both safety and security perspectives when performing a risk analysis for NPPs in order to assess impacts on the safety by cyber-attacks against the digital I&C systems. The STPA-SafeSec methodology was applied to a test-bed system that simulates a condensate water (CD) system in an NPP. The process of the application up to the development of mitigation strategies is described in detail.