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

• 정보보호학회논문지
• /
• 제24권3호
• /
• pp.561-570
• /
• 2014

원자력 발전소(이하 원전)의 계측제어시스템은 원자력 발전소를 안전하게 운전하기 위한 설비로 아날로그 기술에서 디지털기술로 변하고 있다. 그리고 2010년 이란의 부셰르 원자력 발전소의 원심분리기의 가동을 중단시킨 스턱스넷 공격으로 인해 원전의 사이버공격의 가능성이 많이 증가하고 있다. 하지만 국내외 원전 디지털 계측제어시스템의 사이버 보안 강화를 위해 발간된 규제지침들은 보안요구사항들과 정책 및 절차 수립 방법들에 대하여 기술하고 있으며, 실제 적용 가능한 사이버보안 기술을 개발하기 위한 지침으로는 사용하기에 적합하지 않다. 이러한 이유로 원전 디지털 계측제어시스템의 보안을 강화 할 수 있는 원전에 특화된 사이버보안 기술 개발이 필요하다. 이에 본 논문은 원전에 특화된 사이버보안 기술 개발을 위한 기술 개발 체계를 제안하고, 이를 KINCS 사업에서 개발된 공학적안전설비-기기계통에 적용하였다.

• Nuclear Engineering and Technology
• /
• 제37권3호
• /
• pp.207-220
• /
• 2005

Nuclear power plants (NPP) are complex socio-technological systems that rely on the success of both hardware and human components. Empirical studies of plant operating experience show that human errors are important contributors to accidents and incidents, and that organizational factors play an important role in creating contexts for human errors. Current probabilistic safety assessments (PSA) do not explicitly model the systematic contribution of organizational factors to safety. As some countries, like the United States, are moving towards increased use of risk information in the regulation and operation of nuclear facilities, PSA quality has been identified as an area for improvement. The modeling of human errors, and underlying organizational weaknesses at the root of these errors, are important sources of uncertainty in existing PSAs and areas of on-going research. This paper presents a review of research into the following questions: Is there evidence that organizational factors are important to NPP safety? How do organizations contribute to safety in NPP operations? And how can these organizational contributions be captured more explicitly in PSA? We present a few past incidents that illustrate the potential safety implications of organizational deficiencies, some mechanisms by which organizational factors contribute to NPP risk, and some of the methods proposed in the literature for performing root-cause analyses and including organizational factors in PSA.

• 한국콘크리트학회:학술대회논문집
• /
• 한국콘크리트학회 2006년도 추계 학술발표회 논문집
• /
• pp.237-240
• /
• 2006

Almost 30 years have been passed since the first nuclear power plant was operated in Korea. Many studies have been actively conducted from the early 1990's in order to develop the deterioration management system for concrete structures in NPPs(Nuclear Power Plants) accordingly. Base on these studies, a systematic deterioration management program has developed and operated since 1997. According to this program, systematic inspections to provide database and evaluation were periodically performed (every overhaul at intervals of $12{\sim}18$ month and every five years). Accumulated deterioration database was usefully utilized for the NPP PSR (Periodic Safety Review). In this paper, the long-term durability and integrity of Kori 1,2 NPP concrete structures which are the oldest ones in Korea were evaluated based on the precise inspection database and regulatory inspection results including compressive strength, depth of carbonation, amount of chlorination and spontaneous potential of reinforcing bar, etc. It was noted that Kori 1,2 NPP structures have not any serious durability problems.

• Nuclear Engineering and Technology
• /
• 제28권3호
• /
• pp.290-298
• /
• 1996

Direct Containment Heating, DCH, is supposed to occur during a core melt-down accident if the primary system pressure is still high at the time of vessel breach in a Nuclear Power Plant (NPP). In this case, DCH is considered to be one of very important severe phenomena during postulated severe accident scenario because of the fast heat transfer rate to atmosphere and the sharp pressure increase in a containment. To reduce the effect of this DCH phenomena, the capture volume wes designed at Ulchin NPP units 3 and 4. But, the effect of this has not been studied extensively. This work consists of experimental and numerical analyses of the effects of capture volume in the cavity on DCH phenomena. The experimental model is a 1/30 scaled-down model of Ulchin NPP units 3 and 4. We used three types of capture volumes to investigate the effect of size. Numerical analysis using CONTAIN 1.2 is performed with the correlation for the dispersed fraction of molten corium from the cavity into the containment derived from the experimental data to examine the effect of capture volume on DCH phenomena in full scale of Ulchin NPP units 3 and 4.

• 방사성폐기물학회지
• /
• 제20권4호
• /
• pp.541-550
• /
• 2022

When decommissioning nuclear power plant (NPP), the first task performed is cost estimation. This is an important task in terms of securing adequate decommissioning funds and managing the schedule. Therefore, many countries and institutions are conducting continuous research and also developing and using many programs for cost estimation. However, the cost estimated for decommissioning an NPP typically differs from the actual cost incurred in its decommissioning. This is caused by insufficient experience in decommissioning NPPs or lack of decommissioning cost data. This uncertainty in cost estimation can be in general compensated for by applying a contingency. However, reflecting an appropriate standard for the contingency is also difficult. Therefore, in this study, data analysis was conducted based on the contingency guideline suggested by each institution and the actual cost of decommissioning the NPP. Subsequently, TLG Service, Inc.'s process, which recently suggested specific decommissioning costs, was matched with ISDC (International Structure for Decommissioning Costing)'s work breakdown structure (WBS). Based on the matching result, the guideline for applying the contingency for ISDC's WBS Level 1 were presented. This study will be helpful in cost estimation by applying appropriate contingency guidelines in countries or institutions that have no experience in decommissioning NPPs.

• 한국농림기상학회지
• /
• 제1권1호
• /
• pp.1-11
• /
• 1999

작물의 수량은 재배하는 식물의 특성과 토양 그리고 기후 등 환경에 의하여 지배된다. 주곡인 쌀 수확량의 지역성과 변이성을 알아내기 위하여 기상청의 기상 자료와 농림부의 쌀생산량 통계 자료를 수집 분석하였다. 기상 자료로부터 순복사량, 증발산량 및 순1차 생산력지수 NPP를 산출하고, Jung의 모형을 이용하여 우리 나라 각 지역의 쌀 생각량을 산출하고, 이를 실생산량과 비교하였다. 7, 8월 기온의 장기 변이를 검토한 결과, 수원의 경우 장주기는 15.1년, 단주기는 7.4년으로 나타났고, 대구의 장주기는 32.9년, 단주기는 4.1년으로 나타났다. 장주기는 대구가 수원 보다 약 2배이상으로 주기성이 강했고, 단주기는 반대로 수원이 대구보다는 주기성이 강하게 나타났다. 한국의 67개 지점에서 순1차생산력지수인 NPP와 총생산력지수 GPP를 추정 결과, 순 복사량이, 16개 지점에서 기온, 1개 지점에서 강수량이 NPP의 제한 요소로 작용하는 것으로 나타났다. 순 복사량은 한국에서의 자연 생산력에 1차적으로 주된 제한 요인으로서 작용하였고, 2차적인 제한 요인는 주로 기온이 작용하였다. 남한 지역의 NPP는 10.87~17.52 Mg ha$^{-1}$, GPP가 18.63~36.31 Mg ha$^{-1}$의 범위이었고, 평균은 NPP와 GPP가 각각 14.69 Mg ha$^{-1}$, 27.94 Mg ha$^{-1}$의 값을 나타냈다. 북한 지역의 경우에는 NPP가 6.47~15.50Mg ha$^{-1}$, GPP가 10.08~24.64 Mg ha$^{-1}$의 범위이었고, 평균은 NPP와 GPP가 각각 12.59 Mg ha$^{-1}$, 13.62 Mg ha$^{-1}$의 값이 나타났다. Jung의 모델에 의하여 97년과 98년의 쌀 생산량을 추정한 결과 실제 쌀 생산량과 근접하였다. 경상도 지역은 타 지역에 비해 실측치보다 예측치가 높게 평가되었고, 추정 생산량과 실제 생산량간 사이에 상관이 없었다. 이 지역에 대한 모델의 수정이 필요하며, 순복사량과 강수량 요인이 고려되면 좀 더 정확한 분포도가 작성될 수 있을 것이다.

• Nuclear Engineering and Technology
• /
• 제34권4호
• /
• pp.301-313
• /
• 2002

This paper proposes a quantitative approach to modeling the information processing of NPP operators. The aim of this work is to derive the amount of the information processed during a certain control task. The focus will be on i) developing a model for information processing of NPP operators and ii) quantifying the model. To resolve the problems of the previous approaches based on the information theory, i.e. the problems of single channel approaches, we primarily develop the information processing model having multiple stages, which contains information flows. Then the uncertainty of the information is quantified using the Conant’s model, 3 kind of information theory.

• Nuclear Engineering and Technology
• /
• 제54권4호
• /
• pp.1153-1160
• /
• 2022

The application of video processing techniques are useful for the safety of nuclear power plants by tracking the people online on video to estimate the dose received by staff during work in nuclear plants. Nuclear reactors remotely visually controlled to evaluate the plant's condition using video processing techniques. Internal reactor components should be frequently inspected but in current scenario however involves human technicians, who review inspection videos and identify the costly, time-consuming and subjective cracks on metallic surfaces of underwater components. In case, if any frame of the inspection video degraded/corrupted/missed due to noise or any other factor, then it may cause serious safety issue. The problem of missing/degraded/corrupted video frame estimation is a challenging problem till date. In this paper a systematic literature review on video processing techniques is carried out, to perform their suitability analysis for NPP applications. The limitation of existing approaches are also identified along with a roadmap to overcome these limitations.

• 한국방사성폐기물학회:학술대회논문집
• /
• 한국방사성폐기물학회 2018년도 춘계학술논문요약집
• /
• pp.212-213
• /
• 2018