• Nuclear Engineering and Technology
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• 제55권11호
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• pp.4134-4145
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• 2023

This paper proposes strain-based failure model of A533B1 pressure vessel steel to simulate failure, followed by application to OECD lower head failure (OLHF) test simulation for experimental validation. The proposed strain-based failure model uses simple constant and linear functions based on physical failure modes with the critical strain value determined either using the lower bound of true fracture strain or using the average value of total elongation depending on the temperature. Application to OECD Lower Head Failure (OLHF) tests shows that progressive deformation, failure time and failure location can be well predicted.

• Nuclear Engineering and Technology
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• 제55권11호
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• pp.4146-4158
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• 2023

This paper proposes a combined plastic and creep constitutive model of A533B1 pressure vessel steel to simulate progressive deformation of nuclear pressure vessels under severe accident conditions. To develop the model, recent tensile test data covering a wide range of temperatures (from RT to 1,100 ℃) and strain rates (from 0.001%/s to 1.0%/s) was used. Comparison with experimental data confirms that the proposed combined plastic and creep model can well reflect effects of temperature and strain rate on tensile behaviour up to failure. In the companion paper (Part II), the proposed model will be used to simulate OECD lower head failure (OLHF) test data.

• 한국산업융합학회 논문집
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• 제21권6호
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• pp.395-408
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• 2018

Even after the Fukushima nuclear accident in 2011, the rate of production of electric energy using nuclear energy is increasing, but there is a great danger such as the radioactive waste produced when using nuclear power, the catastrophic accident of nuclear power plant, and connection with nuclear weapons. In particular, Cs present in the ionic form of alkaline elements has a long half-life (30.17 years) because it is readily absorbed by the organism and emits intense gamma rays, thus presenting a serious radiation hazard. Therefore, it must be completely removed before it can be released into the natural ecosystem, because it can adversely affect not only humans but also natural ecosystems. Many adsorbents and ion exchangers which have high Cs removal efficiency have been used in recent years to completely separate and remove by self separation in water. Many adsorbents and ion exchangers which have high Cs removal efficiency have been used in recent years to completely separate and remove by self separation in water. In addition, researches have been doing to synthesize magnetic materials with adsorbents such as HCF and PB, and it shows a great effect in the removal rate of Cs present in wastewater or the maximum Cs adsorption amount. In particular, when a magnetic material was applied, excellent results were obtained in which only Cs was selectively removed from other cations. However, new problems such as applicability in the sea where Cs is directly released, applicability in various pH ranges, and failure to preserve the magnetizing force possessed by the magnetic body have been found. However, researches using ferromagnetic field with stronger magnetic properties than those of magnetic bodies is considered to be insufficient. Therefore, it is considered that if the researches combining the ferromagnetic field with the magnetization ability and functional adsorbents more actively, the radioactive material Cs which adversely affects the natural ecosystem can be effectively removed.

• Nuclear Engineering and Technology
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• 제52권7호
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• pp.1462-1470
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• 2020

Reliability in safety-critical systems and equipment is of vital importance, so the probabilistic safety assessment (PSA) has been widely used for many years in the nuclear industry to address reliability in a quantitative manner. As many nuclear power plants (NPPs) become digitalized, evaluating the reliability of safety-critical software has become an emerging issue. Due to a lack of available methods, in many conventional PSA models only hardware reliability is addressed with the assumption that software reliability is perfect or very high compared to hardware reliability. This study focused on developing a new method of safety-critical software reliability quantification, derived from hardware-software integrated environment testing. Since the complexity of hardware and software interaction makes the possible number of test cases for exhaustive testing well beyond a practically achievable range, an importance-oriented testing method that assures the most efficient test coverage was developed. Application to the test of an actual NPP reactor protection system demonstrated the applicability of the developed method and provided insight into complex software-based system reliability.

• 기술혁신연구
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• 제20권3호
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• pp.1-28
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• 2012

본 연구에서는 시나리오 기반의 전략적 미래예측을 통하여 2030년경 우리나라의 원전산업 분야를 정성적으로 분석하였다. 구체적으로 STEEP맵 작성과 네트워크 분석(Network Analysis)을 활용하여 다차원적인 관점에서 미래원전산업 분야 환경변화 영향요인간의 관계성을 규명하였다. 이어 시나리오 기법을 활용하여 미래원전산업의 핵심 불확실성 요인(Key Uncertainty Factor: KUF)을 중심으로 예상 가능한 3가지의 전략적 시나리오 (Optimistic, Business as usual, Pessimistic)를 생성하고, 해외 원전수출을 위해 정부가 시급히 추진해야 될 시나리오별 공통전략과 최대 위험회피 전략도 함께 제시하였다. 본 연구결과를 통해 에너지 가격, 세계 경기 동향, 원전기술 경쟁력, 원전 마케팅 능력 등이 미래 원전산업 분야의 핵심 불확실성 요인으로 작용함을 알 수 있었다. 또한, 실효성 있는 미래원전 산업의 수출전략 마련을 위해서는 '원전 안전 등 기술력 확보', '원전 인력 확보', '우라늄 등 안정적 자원 확보' 및 '원전 수용성 증대'등에 관한 전략 추진이 중요 정책과제로 상정되어야 함을 제안 하였다. 끝으로 이러한 연구결과에 따른 시사점과 연구의 한계에 대하여 논의하였다.

• 한국시뮬레이션학회논문지
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• 제24권4호
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• pp.1-9
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• 2015

원자력 분야에서 안전관련(safety-related) 소프트웨어의 활용이 점차 확대됨에 따라서, 그에 상응하는 소프트웨어 안전과 신뢰도 향상을 위한 방안 연구가 지난 10여년 전부터 활발히 진행되고 있다. 원전 계측제어시스템(MMIS)은 원자력 발전소의 두뇌와 신경망에 해당하는 기능을 수행하고 있고 첨단 디지털 장비들로 구성된다. 따라서 원전 계측제어시스템의 소프트웨어 오류는 원자력 발전소 운전에 지장을 초래할 수 있고, 오동작으로 인한 발전소 정지로 경제적 손실을 초래할 수 있다. 소프트웨어 확인 및 검증(verification and validation, V&V)은 소프트웨어 품질을 향상시킬 수 있는 소프트웨어 공학의 분야로 알려져 있고, 원자력 산업계에서는 소프트웨어 생명주기에 따른 철저한 V&V 활동을 이행하고 준수할 것을 법규로 규정하고 있다. V&V 활동은 소프트웨어 전 생명주기에 따라 분석과 시험 활동들의 조합으로 다른 품질관련 공학 업무를 보완하는 역할을 한다. 본 논문에서는 명세 평가, 요건 추적, 소스코드 리뷰, 및 소프트웨어 시험을 통한 최적화된 안전관련 소프트웨어 V&V 방법론에 기반한 소프트웨어 품질 향상 방안과 단계별로 적합한 도구를 활용하여 효율성을 확보할 수 있는 방안을 제시하고자 한다. 제안된 방법론은 실제 신한울 1,2호기 원자력발전소 MMIS 시스템에 적용되어 입증되었다.

• 한국경영과학회지
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• 제37권3호
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• pp.135-150
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• 2012

This paper presents a portfolio model for a long-term power generation mix problem. The proposed portfolio model evaluates generation mix by considering the tradeoffs between the expected cost for power generation and its variability. Unlike conventional portfolio models measuring variance, we introduce Conditional Value-at-Risk (CVaR) in designing the variability with aims to considering events that are enormously expensive but are rare such as nuclear power plant accidents. Further, we consider uncertainties associated with future electricity demand, fuel prices and their correlations, and capital costs for power plant investments. To obtain an objective generation by each energy source, we employ the sample average approximation method that approximates the stochastic objective function by taking the average of large sample values so that provides asymptotic convergence of optimal solutions. In addition, the method includes Monte Carlo simulation techniques in generating random samples from multivariate distributions. Applications of the proposed model and method are demonstrated through a case study of an electricity industry with nuclear, coal, oil (OCGT), and LNG (CCGT) in South Korea.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2005년도 제36회 하계학술대회 논문집 D
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• pp.2603-2605
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• 2005

This paper describes an experience on the equipment qualification of CRCS(control rod control system) that has been developed for nuclear power plants. A very high level criteria should be satisfied for the equipment to be used for nuclear power plants. We have developed a CRCS that is aimed to be applied to commercial plants. This system adopts a duplex system structure that is based on the state-of-the-art digital technology so that it has higher reliability than the existing systems. The CRCS has been tested at a licensed testing organization and finally qualified. In this paper, the procedures and some trial-and-errors we have been through in the qualification process are explained. It is expected that our experience will be a helpful tips to the industry that are developing various systems for safety-critical plants.

• Earthquakes and Structures
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• 제13권6호
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• pp.561-572
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• 2017

Seismic base isolation has been accepted as one of the most popular design procedures to protect important structures against earthquakes. However, due to lack of information and experimental data the application of base isolation is quite limited to nuclear power plant (NPP) industry. Moreover, the effects of inelastic behavior of soil beneath base-isolated NPP have raised questions to the effectiveness of isolation device. This study applies the wavelet analysis to investigate the effects of soil-structure interaction (SSI) on the seismic response of a base-isolated NPP structure. To evaluate the SSI effects, the NPP structure is modelled as a lumped mass stick model and combined with a soil model using the concept of cone models. The lead rubber bearing (LRB) base isolator is used to adopt the base isolation system. The shear wave velocity of soil is varied to reflect the real rock site conditions of structure. The comparison between seismic performance of isolated structure and non-isolated structure has drawn. The results show that the wavelet analysis proves to be an efficient tool to evaluate the SSI effects on the seismic response of base-isolated structure and the seismic performance of base-isolated NPP is not sensitive to the effects in this case.

• 기술사
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• 제44권6호
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• pp.40-44
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• 2011

Nuclear energy in Korea began in 1958, when the Korea's atomic energy act was formulated and the relevant organizations were founded. Since then, notwithstanding the two catastrophe like TMI and Chernobyl accident, Korea made a wise decision to expand the peaceful uses of the nuclear energy as well as to localize the essential nuclear design technology of fuel and nuclear steam supply system. This decision resulted in the success of export of nuclear power plants as well as research reactor in 2010s. The Korea's nuclear policy, which well utilized 'international crisis in nuclear business' as 'opportunity of Korea to get. nuclear technology', is believed nice policy as a role model of nuclear new-comer countries. Based upon the success story of localization of nuclear technology, Korea had an eye for a niche market, which was a basis of development of SMART, Korea-made integral PWR. The operation of a SMART plant can sufficiently provide not only electricity but also fresh water for 100,000 residents. Last two years, Korea's nuclear industry team led by the Korea Atomic Energy Research Institute completed the standard design of SMART and applied to the Korea's regulatory body for standard design approval. Now the Korea's licensing authority is reviewing the design with the relevant documents, and the design team is doing its best to realize its hope to get the approval by the end of this year. From next year, the SMART business including construction and export will be explored by the KEPCO consortium.