1985 - Volume 27, Issue 3 | by Konstantinov, L.; Joosten, J.; Neboyan, V. (International Atomic Energy Agency, Vienna (Austria). Dept. of Nuclear Energy and Safety)
This article mentions a number of innovations and electronic tools, which are influencing nuclear plant operations. Examples are: The incorporation of digital computer devices in safety systems. The application of noise analysis techniques to serveillance systems of nuclear
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1985 - Volume 27, Issue 3 | by Gilbert, R.S. (Atomic Energy of Canada Ltd., Sheridan Park, Ontario. Electronic Systems Branch)
CANDU stations, as well as others, are now using computer-based logic for safety as well as control functions. In CANDU plants these new safety-related applications incorporate the experience that has been gained using computers for overall plant control. This movement to use
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1985 - Volume 27, Issue 3 | by Buettner, W.E. (Gesellschaft fuer Reaktorsicherheit m.b.H. (GRS), Garching (Germany, F.R.))
This article describes the development of some computerized operator support systems in the FRG with the main emphasis on safety aspects. The tasks of the systems are to: Log and record disturbances and accidents. Reduce the information load and present only essential alarms and
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1985 - Volume 27, Issue 3 | by Perkins, T. (Singer Co., Silver Spring, MD (USA). Link Simulation Systems Div.)
The complexity of today's plants requires that a simulator be the principle tool a qualified instructor uses to teach and to assess an operator's ability to perform under normal and abnormal plant conditions. However, acquisition of a full-scope, plant-specific simulator is just
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1985 - Volume 27, Issue 3 | by Furet, J. (CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. d'Electronique et d'Instrumentation Nucleaire)
Since the beginning of the 1980s, the role of human factors in nuclear plant instrumentation and control has taken added emphasis, mainly because of the Three Mile Island accident and advances in data processing, display equipment, and automatic programmable devices. TMI clearly
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1985 - Volume 27, Issue 3 | by Moore, T. (Electric Power Research Inst., Palo Alto, CA (USA))
In many industrial applications of robots, the objective is to replace human workers with machines that are more productive, efficient, and accurate. But for nuclear applications, the objective is not so much to replace workers as it is to extend their presence - for example, to
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1985 - Volume 27, Issue 3 | by Uematsu, K. (Power Reactor and Nuclear Fuel Development Corp. (Japan))
This article introduces and briefly reviews some of the remote and automated technologies that have been or are being developed at the Tokai reprocessing plant, the associated high-level liquid waste (HLLW) vitrification plant, and Japanese nuclear power plants. The reprocessing
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1985 - Volume 27, Issue 3 | by Rosen, M.; Jankowski, M. (International Atomic Energy Agency, Vienna (Austria). Div. of Nuclear Safety)
The Three Mile Island (TMI-2) accident in 1979 accelerated the process of obtaining and applying the best technical information to estimate the release of radioactive material during postulated severe accidents in commercial light-water reactors. Particular emphasis has been
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1985 - Volume 27, Issue 3 | by Lederman, L. (International Atomic Energy Agency, Vienna (Austria). Div. of Nuclear Safety)
The probabilistic methodology in reliability and safety evaluation today is attracting considerable attention in nuclear power and other fields. The presented article reviews the practical results of the probabilistic safety assessment studies done to date. Safety goals, data
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1985 - Volume 27, Issue 3 | by Cullingford, M. (International Atomic Energy Agency, Vienna (Austria). Div. of Nuclear Safety)
PSA is spreading widely throughout the world, with 30 IAEA Member States having active programmes in this area. The main reason for its popularity is that it offers insights critical in the safety decision-making process available from no other method. It allows power plant
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