• 한국언론정보학보
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• 제76권
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• pp.124-150
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• 2016

이 연구는 후쿠시마 원전 사고 이전과 이후를 비교해 우리나라 원전 보도의 일반적 특성과 보도 프레임 차이를 확인하기 위한 것이다. 이를 위해 중앙 일간신문과 원전 소재 지역 일간신문을 선정해 이들 신문이 게재한 원전 관련 기사에 대한 내용 분석을 실시했다. 연구 결과, 후쿠시마 원전 사고 이후 우리나라 원전에 대한 보도는 크게 늘어난 것으로 나타났다. 또한 이전에 주로 경제적 측면이 강조됐던 우리나라 원전 보도는 후쿠시마 원전 사고 이후 사회적 차원이 강조되기 시작했다. 그리고 우리나라 원전 보도 기사가 주요 기사로 다뤄지는 계기가 됐다. 한편 후쿠시마 원전 사고 이후 우리나라 원전 보도의 프레임 역시 크게 변화했다. 당연하게도 환경 안전 프레임이 크게 증가한 것으로 나타났다. 이는 후쿠시마 원전 사고를 계기로 우리나라 원전의 안정성과 관련된 보도가 대폭 늘어났기 때문으로 보인다. 특히 원전 소재 지역의 일간신문에서 환경 안전 프레임은 후쿠시마 원전 사고 이전에도 다른 프레임과 비교해 가장 많은 29.3%였는데, 그 이후에는 77.6%로까지 증가한 것으로 확인됐다.

• Nuclear Engineering and Technology
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• 제49권2호
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• pp.313-326
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• 2017

The systematic management of plant risk is crucial for enhancing the safety of nuclear power plants and for designing new nuclear power plants. Accident sequence precursor (ASP) analysis may be able to provide risk significance of operational experience by using probabilistic risk assessment to evaluate an operational event quantitatively in terms of its impact on core damage. In this study, an ASP methodology for two operation mode, full power and low power/shutdown operation, has been developed and applied to significant accident precursors that may occur during the operation of nuclear power plants. Two operational events, loss of feedwater and steam generator tube rupture, are identified as ASPs. Therefore, the ASP methodology developed in this study may contribute to identifying plant risk significance as well as to enhancing the safety of nuclear power plants by applying this methodology systematically.

• Nuclear Engineering and Technology
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• 제54권4호
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• pp.1261-1270
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• 2022

This study was conducted to investigate the possibility of using gaze entropy to evaluate an operator's situation awareness in an emergency accident situation of a nuclear power plant. Gaze entropy can be an effective measure for evaluating an operator's situation awareness at a nuclear power plant because it can express gaze movement as a single comprehensive number. In order to determine the relationship between situation awareness and gaze entropy for an emergency accident situation of a nuclear power plant, an experiment was conducted to measure situation awareness and gaze entropy using simulators created for emergency accident situations LOCA, SGTR, SLB, and LOV. The experiment was to judge the accident situation of nuclear power plants presented in the simulator. The results showed that situation awareness and Shannon, dwell time, and Markov entropy had a significant negative correlation, while visual attention entropy (VAE) did not show any significant correlation with situation awareness. The results determined that Shannon entropy, dwell time entropy, and Markov entropy could be used as measures to evaluate situation awareness.

• 과학교육연구지
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• 제37권2호
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• pp.294-309
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• 2013

이 연구에서는 초등 예비교사들의 과학과 관련된 사회적 문제에 대한 인식을 알아보았다. 연구를 위해 SSI와 관련된 구체적인 이슈로 후쿠시마 원전 사고를 이용하였다. 연구에는 교원양성대학에 재학중인 대학교 2학년생 12명이 참여하였으며, 연구 참여자 모두는 초등학교 과학 교육과정에 대한 내용으로 구성되어 있는 초등 과학교육론을 수강하고 있는 학생들이었다. 연구결과 초등 예비교사들은 모두 후쿠시마 원전 사고에 대해 인지하고 있었으며, 원전 사고에 대해 다양한 매체를 통해 접하고 있음을 알 수 있었다. 특히 인터넷을 많이 사용하는 대학생이어서인지 다른 매체에 비해 인터넷을 통해 원전 사고에 대한 내용을 많이 접하고 있었으며, 또한 인터넷을 통해 추가적인 정보를 얻기도 하였다. 그러나 초등 예비교사는 원전 사고에 대해 인지하고 있는 것과는 달리 많은 정보를 갖고 있지는 않았으며, 원전 사고와 같은 SSI에 대해 평소 관심을 갖고 있거나 교육을 받은 경험을 미비했다. 원전 사고와 같은 SSI에 대해 관심은 없으나 원전 사고와 같은 과학적인 문제들이 사회에 밀접한 영향을 미친다는 것은 인식하고 있는 것으로 나타났다. 아울러 현행 교육과정에 SSI 교육이 적용되어야 한다는 점에서도 모두 공감하고 있었으며, 적용되지 않고 있다는 점에 대해서도 문제인식을 같이 하였다. 이상의 연구 결과를 보면, 과학교육의 목표 중에 하나인 과학의 본성을 이해시키는 측면과 과학 교과에 대한 흥미 제고를 위해서라도 SSI 교육에 더욱 활발한 연구뿐만 아니라 정규 교육과정에의 적용은 매우 중요하며 시급하다고 할 수 있다.

• Nuclear Engineering and Technology
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• 제55권2호
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• pp.493-505
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• 2023

Comprehensive condition monitoring of large industry systems such as nuclear power plants (NPPs) is essential for safety and maintenance. In this study, we developed novel system-scale diagnostic technology based on deep-learning and IR thermography that can efficiently and cost-effectively classify system conditions using compact Raspberry Pi and IR sensors. This diagnostic technology can identify the presence of an abnormality or accident in whole system, and when an accident occurs, the type of accident and the location of the abnormality can be identified in real-time. For technology development, the experiment for the thermal image measurement and performance validation of major components at each accident condition of NPPs was conducted using a thermal-hydraulic integral effect test facility with compact infrared sensor modules. These thermal images were used for training of deep-learning model, convolutional neural networks (CNN), which is effective for image processing. As a result, a proposed novel diagnostic was developed that can perform diagnosis of components, whole system and accident classification using thermal images. The optimal model was derived based on the modern CNN model and performed prompt and accurate condition monitoring of component and whole system diagnosis, and accident classification. This diagnostic technology is expected to be applied to comprehensive condition monitoring of nuclear power plants for safety.

• Nuclear Engineering and Technology
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• 제49권3호
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• pp.632-637
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• 2017

Even though the potential for an accident in nuclear power plants is very low, multiple emergency plans are necessary because the impact of such an accident to the public is enormous. One of these emergency plans involves a robotic system for investigating accidents under conditions of high radiation and contaminated air. To develop a robot suitable for operation in a nuclear power plant, we focused on eliminating the three major obstacles that challenge robots in such conditions: the disconnection of radio communication, falling on uneven floors, and loss of localization. To solve the radio problem, a Wi-Fi extender was used in radio shadow areas. To reinforce the walking, we developed two- and four-leg convertible walking, a floor adaptive foot, a roly-poly defensive falling design, and automatic standing recovery after falling methods were developed. To allow the robot to determine its location in the containment building, a bar code landmark reading method was chosen. When a severe accident occurs, this robot will be useful for accident condition monitoring. We also anticipate the robot can serve as a workman aid in a high radiation area during normal operations.

• Nuclear Engineering and Technology
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• 제49권2호
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• pp.426-433
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• 2017

This paper describes the development process, the innovative techniques used and insights gained from the latest integrated, full scope, multistate Level 2 PSA analysis conducted at the Leibstadt Nuclear Power Plant (KKL), Switzerland. KKL is a modern single-unit General Electric Boiling Water Reactor (BWR/6) with Mark III Containment, and a power output of $3600MW_{th}/1200MW_e$, the highest among the five operating reactors in Switzerland. A Level 2 Probabilistic Safety Assessment (PSA) analyses accident phenomena in nuclear power plants, identifies ways in which radioactive releases from plants can occur and estimates release pathways, magnitude and frequency. This paper attempts to give an overview of the advanced modeling techniques that have been developed and implemented for the recent KKL Level 2 PSA update, with the aim of systematizing the analysis and modeling processes, as well as complying with the relatively prescriptive Swiss requirements for PSA. The analysis provides significant insights into the absolute and relative importances of risk contributors and accident prevention and mitigation measures. Thanks to several newly developed techniques and an integrated approach, the KKL Level 2 PSA report exhibits a high degree of reviewability and maintainability, and transparently highlights the most important risk contributors to Large Early Release Frequency (LERF) with respect to initiating events, components, operator actions or seismic component failure probabilities (fragilities).

• 디지털산업정보학회논문지
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• 제16권2호
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• pp.61-68
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• 2020

Nuclear power plants have a lower cost of power generation, and they are more eco-friendly than other power generation plants. Also, we need to prepare nuclear plant accidents because of their severe damage. In the event of a safety accident, such as a radiation leak, by applying a wireless sensor network to a nuclear power plant, many sensor nodes can be used to monitor radiation and transmit information to an external base station to appropriately respond to the accident. However, applying a wireless sensor network to nuclear power plants requires routing protocols that consider the sensor network size and bypass obstacles such as plant buildings. In general, the hierarchical-based routing protocols are efficient in energy consumption. In this study, we look into the problems that may occur if hierarchical-based routing protocols are applied to nuclear power plants and propose improved routing protocols to solve these problems. Simulation results show that the proposed routing protocol is more effective in energy consumption than the existing LEACH protocol.

• 한국압력기기공학회 논문집
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• 제5권2호
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• pp.35-39
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• 2009

In this study, Event Type Analysis System (ETAS) is developed for the accident evaluation in nuclear power plant. The ETAS system can be used in supporting regulator and/or operator under event situation in nuclear power plants. The ETAS system can categorize the all transient events to 3 categories such as Down-2000, Down-2173, and Slow Fluctuation. We develop the program structure for ETAS system and web-based ETAS system. The ETAS system will be used as sub module of Knowledge-Based Event Evaluation Network (K-EvENT) which is developing for the against the accident in nuclear power plants.

• 대한안전경영과학회지
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• 제7권4호
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• pp.85-99
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• 2005

The main objective of this paper is to search whether containment vessel's best pressure may increase until how long when loss of coolant accident (LOCA) happened in containment vessel of Ulchin nuclear power plant 1 and 2. Another goal of this research is to find the influential factors that increase containment vessel pressure. Model for this research is Ulchin nuclear power plant 1 with 10 cycles. Data were collected by simulator of Ulchin nuclear power plant 1 and design of experiment was used for data analysis. For the experiment, seven factors that are going to influence in containment vessel pressure were chosen. It was found that fatter which influences in early rise of containment vessel pressure after LOCA is only explosion size. Also, containment vessel's best pressure (3.74 bar.a) was much lower than limit (4.86 bar.a) of FSAR (Final Safety Analysis Report).