• 한국정밀공학회:학술대회논문집
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• 한국정밀공학회 2009년도 추계학술대회 논문집
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• pp.291-292
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• 2009

• 대한원격탐사학회지
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• 제27권4호
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• pp.467-480
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• 2011

본 연구는 AVHRR(Advanced Very High Resolution Radiometer)과 MODIS(MODerate-resolution Imaging Spectroradiometer) 위성관측을 바탕으로 산출된 남한지역의 장기간(1981-2006년) 순 일차생산량(Net Primary Production, NPP)의 시공간적 변화를 분석하고 그 변화에 영향을 미치는 기후요소와의 상관성을 분석하였다. 남한지역의 AVHRR과 MODIS에서는 연간순 열차생산량이 AVHRR의 경우 893-1068 $g{\cdot}C/m^2$ /yr과 MODIS의 경우 610-695 $g{\cdot}C/m^2$/yr로 나타나고 있으며 두 자료는 통계적으로 약 325 $g{\cdot}C/m^2$/yr 의 차이를 보이고 있다. 해상도 등의 차이가 있으나 지상 관측과 비교한 결과 MODIS 센서에 의한 관측이 보다 근접한 결과를 보이는 것으로 나타났다. 위성관측자료 분석결과 NPP 값은 식생의 밀도가 높은 산림지역 및 연평균기온이 높은 지역에서 큰 것으로 나타났다. 두개의 위성센서로 산출된 순 열차생산량은 경년변화가 다소 크지만, 각각 장기간에 걸쳐 서서히 증가하고 있는 것으로 나타났으며 1981-2000년 동안 AVHRR에서 매년 평균 2.14 $g{\cdot}C/m^2$/yr, 2000-2006년 동안 MODIS에서 매년 평균 6.08 $g{\cdot}C/m^2$/yr 만큼 증가하였다. 특히 남서해안 지역은 두 위성관측결과 모두 순 일차생산량의 증가가 상대적으로 높았다. 토지피복 지도와 대조결과 그 이유는 논 밭 등의 관개와 비료시용에 의한 농작물의 생산성 증대와 관계가 있는 것으로 추정된다. NPP값은 월별 강수량 및 평균기온에 밀접한 관계가 있는 것으로 확인되었으며, 특히 남한지역의 여름몬순시기에서 강수량과 기온이 모두 가장 큰 상관관계를 보이고 있다. NPP 절대값의 차이 외에도 두 센서로 산출된 순 일차생산량과 기후요소와의 상관성 등의 차이는 두 자료의 토양호흡 등을 포함하는 등 위성자료 복원과정 및 관련 모텔의 차이에 의해 발생하는 것으로 사료된다. 또한 향후 보다 정확한 순 일차생산량을 계산하기 위해 복원과정에서 기상 실측자료 및 보다 현실적인 토지피복 등을 고려해야 할 것이다.

• Nuclear Engineering and Technology
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• 제51권4호
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• pp.1176-1179
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• 2019

Measurements of activity concentrations of radionuclides in atmospheric releases were performed in 2017-2018 at vent stacks of seven Russian nuclear power plants. The selected instruments and research methods, with detection limits significantly lower than the existing detection limit of Russian NPPs routine control, allowed to reliably determine up to 26 radionuclides. Analysis of experimental data allows to determine the list of radionuclides for calculation the effective dose rates to public and the permissible annual discharge levels for each Russian NPP. Radiocarbon is determined as major contributor for the dose from the atmospheric releases of LWGR reactors - up to 98% for EGP-6 and RBMK-1000 (Smolensk NPP) reactors. For PWR reactors (VVER) radionuclides contribution to the annual dose from atmospheric releases is more complicated, but, in general, dose is formed by tritium, $^{14}C$ and noble gases. The special monitoring results with ranking of measured radionuclides according to their contribution to the effective dose makes it possible to optimize the list of controlled radionuclides in airborne releases of Russian NPPs from 94 to 8-16 for different NPPs.

• Nuclear Engineering and Technology
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• 제41권3호
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• pp.247-270
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• 2009

This paper reviews studies on information searching behavior in process control systems and discusses some implications learned from previous studies for use in human factors studies on nuclear power plants (NPPs) main control rooms (MCRs). Information searching behavior in NPPs depends on expectancy, value, salience, and effort. The first quantitative scanning model developed by Senders for instrument panel monitoring considered bandwidth (change rate) of instruments as a determining factor in scanning behavior. Senders' model was subsequently elaborated by other researchers to account for value in addition to bandwidth. There is also another type of model based on the operator's situation awareness (SA) which has been developed for NPP application. In these SA-based models, situation-event relations or rules on system dynamics are considered the most significant factor forming expectancy. From the review of previous studies it is recommended that, for NPP application, (1) a set of symptomatic information sources including both changed and unchanged symptoms should be considered along with bandwidth as determining factors governing information searching (or visual sampling) behavior; (2) both data-driven monitoring and knowledge-driven monitoring should be considered and balanced in a systematic way; (3) sound models describing mechanisms of cognitive activities during information searching tasks should be developed so as to bridge studies on information searching behavior and design improvement in HMI; (4) the attention-situation awareness (A-SA) modeling approach should be recognized as a promising approach to be examined further; and (5) information displays should be expected to have totally different characteristics in advanced control rooms. Hence much attention should be devoted to information searching behavior including human-machine interface (HMI) design and human cognitive processes.

• 한국시뮬레이션학회:학술대회논문집
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• 한국시뮬레이션학회 2003년도 추계학술대회 및 정기총회
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• pp.165-171
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• 2003

We have developed Virtual Reality Simulator MMI for operator training. MMI communicates with server model and client PC through OPCServer. We used Dataplant for Soft Panel and Simdiagram which shows more sophisticated and reality colors. We used vector method for MCR images instead of conventional bit-map method to protect images during zoom in and zoom out. VBScript and Components were used for real movements and images of instruments. VRMCR panel is consisted of 12 groups and designed to accommodate user's convenience.

• 전자공학회논문지B
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• 제32B권9호
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• pp.1215-1230
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• 1995

The purpose of this paper is to build a computer vision system that endows an autonomous mobile robot the ability of automatic measuring of the analog and digital meters installed in nuclear power plant(NPP). This computer vision system takes a significant part in the organization of automatic surveillance and measurement system having the instruments and gadzets in NPP under automatic control situation. In the meter image captured by the camera, the meter area is sorted out using mainly the thresholding and the region labeling and the meter value recognition process follows. The positions and the angles of the needles in analog meter images are detected using the projection based method. In the case of digital meters, digits and points are extracted and finally recognized through the neural network classifier. To use available database containing relevant information about meters and to build fully automatic meter recognition system, the segmentation and recognition of the function-name in the meter printed around the meter area should be achieved for enhancing identification reliability. For thus, the function- name of the meter needs to be identified and furthermore the scale distributions and values are also required to be analyzed for building the more sophisticated system and making the meter recognition fully automatic.

• Nuclear Engineering and Technology
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• 제48권5호
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• pp.1206-1218
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• 2016

This article proposes a highly reliable power and communication system that guarantees the protection of essential instruments in a nuclear power plant under a severe accident. Both power and communication lines are established with not only conventional wired channels, but also the proposed wireless channels for emergency reserve. An inductive power transfer system is selected due to its robust power transfer characteristics under high temperature, high pressure, and highly humid environments with a large amount of scattered debris after a severe accident. A thermal insulation box and a glass-fiber reinforced plastic box are proposed to protect the essential instruments, including vulnerable electronic circuits, from extremely high temperatures of up to $627^{\circ}C$ and pressure of up to 5 bar. The proposed wireless power and communication system is experimentally verified by an inductive power transfer system prototype having a dipole coil structure and prototype Zigbee modules over a 7-m distance, where both the thermal insulation box and the glass-fiber reinforced plastic box are fabricated and tested using a high-temperature chamber. Moreover, an experiment on the effects of a high radiation environment on various electronic devices is conducted based on the radiation test having a maximum accumulated dose of 27 Mrad.

• 전기학회논문지
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• 제65권5호
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• pp.836-842
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• 2016

When an accident occurs in the nuclear power plant, the faulted information might mislead to the high possibility of aggravating the accident. At the Fukushima accident, the operators misunderstood that there was no core exposure despite in the processing of core damage, because the instrument information of the reactor water level was provided to the operators optimistically other than the actual situation. Thus, this misunderstanding actually caused to much confusions on the rapid countermeasure on the accident, and then resulted in multiplying the accident propagation. It is necessary to be equipped with the function that informs operators the status of instrument integrity in real time. If plant operators verify that the instruments are working properly during accident conditions, they are able to make a decision more safely. In this study, we have performed various tests for the fault detection sensitivity of an data-driven empirical model to review the usability of the model in the accident conditions. The test was performed by using simulation data from the compact nuclear simulator that is numerically simulated to PWR type nuclear power plant. As a result of the test, the proposed model has shown good performance for detecting the specified instrument faults during normal plant conditions. Although the instrument fault detection sensitivity during plant accident conditions is lower than that during normal condition, the data-drive empirical model can be detected an instrument fault during early stage of plant accidents.

• 지질공학
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• 제21권1호
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• pp.87-95
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• 2011

이 연구는 신월성 원자력발전소 1,2호기(이하 신월성원전) 운영과 함께 국내 원자력관련 이용시설 부지(이하 원자력부지)에 처음 도입될 단층감시시스템의 설치 운영에 필요한 안전요건(즉, 규제 요건, 지침 및 기술기준)을 제공할 목적으로 국내외 단층감시시스템과 그와 유사한 측지시스템의 구축 사례를 수집, 분석하였으며, 단층감시시스템 구축 시 기본적으로 고려하여야 할 기술 사항들을 제시하였다. 단층감시시스템 구축 시 고려해야할 사항들로는 1) 부지고유특성의 이해(잡음 특성 포함), 2) 감시대상에 맞는 설비/설계 선택, 3) 백업시스템 구축, 4) 정례화된 검 교정체제를 통한 계측자료의 품질과 신뢰성 확보, 5) 투명한 운영체계와 정보공개 정책, 6) 장기적으로 안정적인 운영기반 등이 제안되었다.