• 한국안전학회지
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• 제14권2호
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• pp.32-41
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• 1999

If the Leak-Before-Break (LBB) concept is applicable to the nuclear piping design, it is not necessary to consider the dynamic effect due to pipe rupture. Therefore, the construction cost can be significantly reduced by eliminating unnecessary pipe whip restraints and jet impingement devices. The objective of this paper is to develop the Piping Evaluation Diagram (PED) for efficient application of LBB concept to piping system at an initial piping design stage. For this purpose, the 3-D finite element analyses were performed to evaluate the crack stability. And the stress-strain curve based on the pipe material tests were used to calculate the detectable leakage crack length. Finally, the present PED which was composed as a function of NOP load and allowable SSE load, was developed for an application of LBB concept to the safety injection and shutdown cooling line in Korean Next Generation Reactor (KNGR).

• 한국건축시공학회:학술대회논문집
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• 한국건축시공학회 2018년도 춘계 학술논문 발표대회
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• pp.151-152
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• 2018

In the domestic nuclear power industry, concern about safety of nuclear power plants is continuously increased with the Fukushima nuclear power plant accident. In order to enhance the safety of nuclear power plants, it is important to ensure that the power plants are operating with proper margin within the original design bases. Margin management is the process of ensuring that the NPP designer and operator are aware of the physical and operating limits, and potential and probability of failure, for each component in the plant. All components are subject to margin considerations, but the most important components by scope and attention are those related to safety-related systems and NPP safe shutdown.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1997년도 춘계학술발표회논문집(2)
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• pp.477-482
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• 1997

Safe shutdown earthquakes (SSE) of four existing nuclear power plant sites were evaluated by using a probabilistic method. It turned out that the SSE's of the two sites are smaller than those of the rest. Site-specific response spectra were developed for two sites of which SSE's show a comparatively large difference. The result shows that the site-specific response spectrum of one site is higher by a factor of 1.5 than that of the other. The comparison of uniform hazard spectrum and site-specific response spectrum at one of the two sites shows that the both spectra are consistent with each other.

• Nuclear Engineering and Technology
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• 제55권3호
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• pp.861-869
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• 2023

This article proposes a novel approach to measure the performance of Safety-Critical Systems (SCS). Such systems contain multiple processing nodes that communicate with each other is modeled by a Petri nets (PN). The paper uses the PN for the performance evaluation of SCS. A set of ordinary differential equations (ODEs) is derived from the Petri net model that represent the state of the system, and the solutions can be used to measure the system's performance. The proposed method can avoid the state space explosion problem and also introduces new metrics of performance, along with their measurement: deadlock, liveness, stability, boundedness, and steady state. The proposed technique is applied to Shutdown System (SDS) of Nuclear Power Plant (NPP). We obtained 99.887% accuracy of performance measurement, which proves the effectiveness of our approach.

• Nuclear Engineering and Technology
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• 제44권5호
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• pp.459-470
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• 2012

From the PSA point of view, the Fukushima accident of Japan in 2011 reveals some issues to be re-considered and/or improved in the PSA such as the limited scope of the PSA, site risk, etc. KAERI (Korea Atomic Energy Research Institute) has performed researches on the development of an integrated risk assessment framework related to some issues arisen after the Fukushima accident. This framework can cover the internal PSA model and external PSA models (fire, flooding, and seismic PSA models) in the full power and the low power-shutdown modes. This framework also integrates level 1, 2 and 3 PSA to quantify the risk of nuclear facilities more efficiently and consistently. We expect that this framework will be helpful to resolve the issue regarding the limited scope of PSA and to reduce some inconsistencies that might exist between (1) the internal and external PSA, and (2) full power mode PSA and low power-shutdown PSA models. In addition, KAERI is starting researches related to the extreme external events, the risk assessment of spent fuel pool, and the site risk. These emerging issues will be incorporated into the integrated risk assessment framework. In this paper the integrated risk assessment framework and the research activities on the emerging issues are outlined.

• 산업경영시스템학회지
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• 제27권4호
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• pp.1-6
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• 2004

사고 위험성을 고려한 예측 및 의사결정 모형을 구축한다. 시스템을 즉시 운행중지 할 것인지 혹은 계획된 일정기간을 더 운행 한 후 다시 의사결정을 내릴 것인지를 판단하는 방법론에 대해 연구한다. 의사결정을 내리는데 있어서 비용 및 위험에 대한 새로운 정보가 입수되는 대로 이를 반영한다. 예측 모형을 통해 분석된 결과들을 활용해 보다 나은 의사결정을 내리는 방법에 대해 연구한다.

• 전기전자학회논문지
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• 제23권1호
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• pp.68-73
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• 2019

벅 컨버터는 전압 직류 계통(LVDC), 가전 분야 및 전기차 충방전 분야에서 다양하게 적용되고 있는 전력변환장치이며, 일반적으로 벅 컨버터는 부하측에 단락 등 고장 발생시 반도체 스위칭 소자를 개방시켜 벅 컨버터의 운전을 중지시킨다. 그러나 벅 컨버터의 출력단에 인덕터와 캐패시터에 저장된 에너지로 인해 고장 전류가 지속적으로 부하로 전달되는 문제점을 가지고 있다. 본 논문에서는 벅 컨버터의 출력측 저역통과 필터에 일반적인 인덕터 대신 커플드 인덕터(Coupled-inductor)를 사용하여 인덕터에 저장된 전기에너지를 부하단에 공급되지 않도록 소모시키는 구성을 포함하는 벅 컨버터의 새로운 고장전류 고속차단 방식을 제안하며, 제안된 방식은 시뮬레이션을 통해 성능을 검증하였다.

• Nuclear Engineering and Technology
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• 제47권4호
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• pp.443-453
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• 2015

A hybrid safety injection tank (H-SIT) can enhance the capability of an advanced power reactor plus (APR+) during a station black out (SBO) that is accompanied by a severe accident. It may a useful alternative to an electric motor. The operations strategy of the H-SIT has to be investigated to achieve maximum utilization of its function. In this study, the master logic diagram (i.e., an analysis for identifying the differences between an H-SIT and a safety injection pump) and an accident case classification were used to determine the parameters of the H-SIT operation. The conditions that require the use of an H-SIT were determined using a decision-making process. The proper timing for using an H-SIT was also analyzed by using the Multi-dimensional Analysis of Reactor Safety (MARS) 1.3 code (Korea Atomic Energy Research Institute, Daejeon, South Korea). The operation strategy analysis indicates that a H-SIT can mitigate five types of failure: (1) failure of the safety injection pump, (2) failure of the passive auxiliary feedwater system, (3) failure of the depressurization system, (4) failure of the shutdown cooling pump (SCP), and (5) failure of the recirculation system. The results of the MARS code demonstrate that the time allowed for recovery can be extended when using an H-SIT, compared with the same situation in which an H-SIT is not used. Based on the results, the use of an H-SIT is recommended, especially after the pilot-operated safety relief valve (POSRV) is opened.

• Journal of Radiation Protection and Research
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• 제28권2호
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• pp.109-116
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• 2003

본 연구에서는 최근 국내 원자력발전소의 해체시 방사화 생성물 재고량의 평가 필요성이 대두됨에 따라 원자로 수명종로가 가까워지고 있는 고리1호기를 대상으로 원자로 각 구조물의 방사라 생성물 재고량을 ANISN과 ORIGEN2 코드를 이용하여 예비평가를 수행하였다. 코드 입력자료로는 노심에서부터 차폐콘크리트까지 반경방향으로 8개 영역으로 나누어 ANISN 코드를 사용하여 중성자속을 계산하였다. 또한 압력용기의 중성자속 분포를 가지고 주요 핵종의 단일 그룹 반응단면 적을 보정하였다. 본 연구의 결과 압력용기의 경우 원자로 정지시점에서 약 10년까지는 $^{55}Fe,\;^{59}Ni,\;^{63}Ni,\;^{60}Co$ 핵종이 총 방사능의 약 95%정도를 차지하였으며, 약 50년 이상 냉각 후의 총 방사능은 원자로 정지시점과 비교하여 약 0.2 % 이하로 감소하는 것으로 평가되었다. 또한 압력용기의 무게가 210 ton임을 고려해 볼 때, 압력용기의 총 방사화생성물 재고량은 $5.25{\times}10^6GBq$로 계산되었다. 또한 차폐콘크리트의 경우 약 10년 이상 냉각 후의 총 방사능은 원자로 정지시점과 비교하여 1 %이하로 급격히 감소하는 것으로 평가되었다.

• 한국지진공학회논문집
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• 제25권3호
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• pp.129-135
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• 2021

After the manual shutdown of the Wolseong nuclear power plant due to an earthquake in Gyeongju in 2016, anxiety about the earthquake safety of nuclear power plants has become a major social issue. The shear wall structure used as a major structural element in nuclear power plants is widely used as a major structural member because of its high resistance to horizontal loads such as earthquakes. However, due to the complexity of the structure, it is challenging to predict the dynamic characteristics of the structure. In this study, a three-story shear wall structure is fabricated, and the in-structure response characteristics of the shear wall structure are evaluated through shaking table tests. The test is performed using the Gyeongju earthquake that occurred in 2016, and the response characteristics due to the domestic earthquake are evaluated.