• Title/Summary/Keyword: nuclear disaster

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Research on Utilizing Method of CCTV System for Crime Prevention and Safety Accident Reduction (범죄예방 및 안전사고 감소를 위한 CCTV시스템의 활용방안에 관한 연구)

  • Kim, Tae-Hwan
    • Journal of the Society of Disaster Information
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    • v.3 no.1
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    • pp.55-68
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    • 2007
  • Recently, people in cities of developed countries are exposed to unfortified damages of crime and disaster due to urbanization, industrialization and information-oriented era caused by congestion of population in terms of hardware and various social pathology phenomena and frequent and large scale of disaster caused by crime and disorder, which occur in the course of going through nuclear family, a gap between rich and poor and aging society in terms of software. In this regard, demand for security upon individual life and property has been increased but the police that are responsible for the public security does not effectively reduce damage in life and property because their activities are mainly oriented in coping with security accidents more than prevention. Shortage of manpower and budget, retarded equipment, and heavy overwork are the reasons. In order to confront with this kind of situation, we should utilize CCTV system with the purpose of declining possible chances of crime, not for eliminating cause of crime as crime prevention activities to predict danger in advance as a way of prevention and we may expect a role of damage prevention by installing CCTV in places where security accident may possibly happen. In conclusion, there are invasion of privacy, misuse of the system, insufficiency of overall monitoring office management, lack of citizens' understanding and economical allotment of the system installation costs in installation of CCTV system. However. it is necessary to install the CCTV system for effective prevention of crime and prevention activities of security accidents and accurate PR of purposes of installing CCTV to local residents, establishing relevant laws about system misuse, allotment of equipment costs and fees by R&D of the system machinery, cost reduction method of storage, management and replacement, saving costs from co-operative attitude of government, and local autonomous entities and local residents should be involved.

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Implementation of Nuclear Power Plant components Supply Chain Management System based on RFID (RFID를 활용한 원전부품 공급사슬관리시스템 구축 방안)

  • Park, Doo-jin;Ha, Chang-seung;Jung, Lee-sang
    • Proceedings of the Korean Institute of Information and Commucation Sciences Conference
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    • 2012.10a
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    • pp.923-924
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    • 2012
  • Nuclear power is one of energy sources which has the safety and economic feasibility in supply. However, due to the recent disaster in Fukushima, Japan, the safety issue of nuclear power is now come to the fore again. For example, Germany and Italy they cancel some projects on nuclear power launching. In South Korea also, a lot of safety concerns are discussed and small and big accidents occur. Thus, this study suggests the supply chain management system based on RFID to improve safety and efficiency at the same time.

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Seismic performance evaluation of reactor containment building considering effects of concrete material models and prestressing forces

  • Bidhek Thusa;Duy-Duan Nguyen;Md Samdani Azad;Tae-Hyung Lee
    • Nuclear Engineering and Technology
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    • v.55 no.5
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    • pp.1567-1576
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    • 2023
  • The reactor containment building (RCB) in nuclear power plants (NPPs) plays an important role in protecting the reactor systems from external loads as well as preventing radioactive leaking. As we witnessed the nuclear disaster at Fukushima Daiichi (Japan) in 2011, the earthquake is one of the major threats to NPPs. The purpose of this study is to evaluate effects of concrete material models and presstressing forces on the seismic performance evaluation of RCB in NPPs. A typical RCB designed in Korea is employed for a case study. Detailed three-dimensional nonlinear finite element models of RCB are developed in ANSYS. A series of pushover analyses are then performed to obtain the pushover curves of RCB. Different capacity curves are compared to recognize the influence of different material models on the nonlinear behavior of RCB. Additionally, the effects of prestressing forces on the seismic performances of the structure are also investigated. Moreover, a set of damage states corresponding to damage evolutions of the structures is proposed in this study.

A Study on Development of Civil Defense CBR Virtual Training Simulation Scenario (민방위 화생방 가상훈련 시뮬레이션 시나리오 개발 연구)

  • Jung, Tae-Ho;Jang, Jae-Soon;Park, Sang-Hyun
    • Journal of the Korea Safety Management & Science
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    • v.16 no.3
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    • pp.175-183
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    • 2014
  • In spite of international efforts to control nuclear weapons and chemical, biological, and radiological (CBR) weapons, North Korea obtains and sells CBR weapons illegally. As a result, the worldwide threat of CBR weapons is increasing. Unfortunately, civil defense education and training for CBR weapons have not been adopted for real situations because of the long period of absence of an actual combat. In this study, virtual training scenarios that are applied to the simulation were made in 5 steps to cope with CBR situations. These scenarios are expected to have three effects. First, trainings can be improved with experience and education. Second, the problems and health hazards of CBR weapons and supplies can be solved with CBR virtual training simulation experience. Finally, corresponding effects can be recognized and predicted in real situations through roles and mission procedures of simulation scenario.

A review of rotorcraft Unmanned Aerial Vehicle (UAV) developments and applications in civil engineering

  • Liu, Peter;Chen, Albert Y.;Huang, Yin-Nan;Han, Jen-Yu;Lai, Jihn-Sung;Kang, Shih-Chung;Wu, Tzong-Hann;Wen, Ming-Chang;Tsai, Meng-Han
    • Smart Structures and Systems
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    • v.13 no.6
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    • pp.1065-1094
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    • 2014
  • Civil engineers always face the challenge of uncertainty in planning, building, and maintaining infrastructure. These works rely heavily on a variety of surveying and monitoring techniques. Unmanned aerial vehicles (UAVs) are an effective approach to obtain information from an additional view, and potentially bring significant benefits to civil engineering. This paper gives an overview of the state of UAV developments and their possible applications in civil engineering. The paper begins with an introduction to UAV hardware, software, and control methodologies. It also reviews the latest developments in technologies related to UAVs, such as control theories, navigation methods, and image processing. Finally, the paper concludes with a summary of the potential applications of UAV to seismic risk assessment, transportation, disaster response, construction management, surveying and mapping, and flood monitoring and assessment.

Thickness measurements of a Cr coating deposited on Zr-Nb alloy plates using an ECT pancake sensor

  • Jeong Won Park;Bonggyu Ji;Daegyun Ko;Hun Jang;Wonjae Choi
    • Nuclear Engineering and Technology
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    • v.55 no.9
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    • pp.3260-3267
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    • 2023
  • Zr-Nb alloy have been widely used as fuel rods in nuclear power plants. However, from the Fukushima nuclear accident, the weakness of the rod was revealed under harsh conditions, and research on the safety of these types of rods was conducted after the disaster. The method of depositing chromium onto the existing Zr-Nb alloy fuel rods is being considered as a means by which to compensate for the weakness of Zr-Nb alloy rods because chromium is strong against oxidation at high temperatures and has high strength. In order to secure these advantages, it is important to maintain the Cr thickness of the rods and properly inspect the rods before and during their use in power generation. Eddy current testing is a typical means of evaluating the thickness of thin metals and detecting surface defects. Depending on the size and shape of the inspected object, various eddy current sensors can be applied. In particular, because pancake sensors can be manufactured in very small sizes, they can be used for inspections even in narrow spaces, such as a nuclear fuel assembly. In this study, an eddy current technique was developed to confirm the feasibility of Cr coating thickness evaluations. After determining the design parameters of the pancake sensor by means of a FEM simulation, a FPCB pancake sensor was manufactured and the optimal frequency was selected by measuring minute changes in the Cr-coating thickness using the developed sensor.

A Pilot Study on the Building a Digital Twin Platform for Nuclear Plant (디지털 트윈 플랫폼 구축을 위한 가동원전 파일럿 연구)

  • Choi, Doo-Chan;Kim, Sang-Il;Son, Eun-soo;Kim, Jun-soo
    • Proceedings of the Korean Society of Disaster Information Conference
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    • 2023.11a
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    • pp.81-82
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    • 2023
  • 디지털 트윈 플랫폼을 적용하여 가동원전의 화재 안전성을 강화시키고자 한다. 원전에 특화된 화재 감지, 진압 설비를 개발하면서 디지털 트윈에 적용하기 위하여 수집해야 할 데이터에 대한 연구를 수행하고 있다. 본 연구에 대해서 원전에 특화된 공기흡입형 감지모듈과 미분무 소화설비를 개발하고 있으며 제품에 대한 DB를 구축하여 디지털 트윈에 적용시키고자 유니티(Unity) 툴을 이용하여 파일럿 규모의 전기실 화재에 대한 모델링을 수행하였다. 추후 실규모의 소방 시스템을 제작하고 적용 가능한 센서를 통해 데이터를 수집할 것이며, 이를 통해 디지털 트윈 플랫폼을 구축하여 CDF 저감에 기여할 것으로 기대된다.

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Surrogate Model-Based Global Sensitivity Analysis of Components of a Test Mock-Up Nuclear Containment Building subjected to Internal Pressure (내압을 받는 축소규모 원전 격납건물 구성요소의 대리모델 기반 전역 민감도 분석)

  • Son, Hoyoung;Lee, Jong-Ryun;Ju, Bu-Seog
    • Proceedings of the Korean Society of Disaster Information Conference
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    • 2023.11a
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    • pp.303-304
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    • 2023
  • 확률론적 위험성 평가는 하중, 재료특성 등과 같은 불확실성 인자를 고려하여 구조물의 안전성을 평가하는 기법이지만 모든 불확실성을 고려하는 것은 현실적으로 불가능하다. 또한 원전 격납건물은 콘크리트, 철근, 라이너, 텐던이 복잡하게 결합되어 있다. 따라서 전역민감도 분석을 통해 격납건물의 불확실성 인자 검토하고 선정하는 작업은 필요하다. 따라서 본 연구는 대리모델을 기반으로 축소규모 원전 격납건물의 전역 민감도 분석을 수행하고 격납건물의 주요 영향인자를 분석하고자 한다. 유한요소 해석 모델을 기반으로 대리모델의 학습데이터를 생성하였으며 구축된 대리모델의 성능지표를 분석하였을 때 높은 회귀성능을 갖는 것으로 판단된다. 대리모델을 기반으로 전역 민감도 분석을 수행한 결과 콘크리트의 인장균열이 발생하는 내압수준에서 민감도 지수는 콘크리트의 압축강도가 높지만, 전체적인 내압 구간에서 민감도 지수는 텐던의 탄성계수 및 항복강도가 높은 것으로 나타났다.

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Development of an efficient method of radiation characteristic analysis using a portable simultaneous measurement system for neutron and gamma-ray

  • Jin, Dong-Sik;Hong, Yong-Ho;Kim, Hui-Gyeong;Kwak, Sang-Soo;Lee, Jae-Geun;Jung, Young-Suk
    • Analytical Science and Technology
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    • v.35 no.2
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    • pp.69-81
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    • 2022
  • The method of measuring and classifying the energy category of neutrons directly using raw data acquired through a CZT detector is not satisfactory, in terms of accuracy and efficiency, because of its poor energy resolution and low measurement efficiency. Moreover, this method of measuring and analyzing the characteristics of low-energy or low-activity gamma-ray sources might be not accurate and efficient in the case of neutrons because of various factors, such as the noise of the CZT detector itself and the influence of environmental radiation. We have therefore developed an efficient method of analyzing radiation characteristics using a neutron and gamma-ray analysis algorithm for the rapid and clear identification of the type, energy, and radioactivity of gamma-ray sources as well as the detection and classification of the energy category (fast or thermal neutrons) of neutron sources, employing raw data acquired through a CZT detector. The neutron analysis algorithm is based on the fact that in the energy-spectrum channel of 558.6 keV emitted in the nuclear reaction 113Cd + 1n → 114Cd + in the CZT detector, there is a notable difference in detection information between a CZT detector without a PE modulator and a CZT detector with a PE modulator, but there is no significant difference between the two detectors in other energy-spectrum channels. In addition, the gamma-ray analysis algorithm uses the difference in the detection information of the CZT detector between the unique characteristic energy-spectrum channel of a gamma-ray source and other channels. This efficient method of analyzing radiation characteristics is expected to be useful for the rapid radiation detection and accurate information collection on radiation sources, which are required to minimize radiation damage and manage accidents in national disaster situations, such as large-scale radioactivity leak accidents at nuclear power plants or nuclear material handling facilities.

Analysis of loss of cooling accident in VVER-1000/V446 spent fuel pool using RELAP5 and MELCOR codes

  • Seyed Khalil Mousavian;Amir Saeed Shirani;Francesco D'Auria
    • Nuclear Engineering and Technology
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    • v.55 no.8
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    • pp.3102-3113
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    • 2023
  • Following the Fukushima nuclear disaster, the simulation of accidents in the spent fuel pool has become more noticeable. Despite the low amount of decay heat power, the consequences of the accidents in a spent fuel pool (SFP) can be severe due to the high content of long-lived radionuclides and lack of protection by the pressure vessel. In this study, the loss-of-cooling accident (LOFA) for the VVER-1000/V446 spent fuel pool is simulated by employing RELAP5 and MELCOR 1.8.6 as the best estimate and severe accident analysis codes, respectively. For two cases with different total power levels, decay heat of spent fuels is calculated by ORIGEN-II code. For modeling SFP of a VVER-1000, a qualified nodalizations are considered in both codes. During LOFA in SFP, the key sequences such as heating up of the pool water, boiling and reducing the water level, uncovering the spent fuels, increasing the temperature of the spent fuels, starting oxidation process (generating Hydrogen and extra power), the onset of fuel melting, and finally releasing radionuclides are studied for both cases. The obtained results show a reasonable consistency between the RELAP5 and MELCOR codes, especially before starting the oxidation process.