Results 251 to 260 of about 6,592,670 (293)

Mathematical Decision Support Model for the Decommissioning of Nuclear Power Facilities

2018 10th International Congress on Ultra Modern Telecommunications and Control Systems and Workshops (ICUMT), 2018
The paper proposes a structure of a mathematical model for supporting decision-making on the decommissioning of nuclear power facilities. The proposed structure includes a scheme of analysing the various options for decommissioning nuclear power facilities based on a multi-criteria approach.
Valeriy V. Bochkarev, Alexandr V. Kryanev, Dmitry S. Smirnov   +2 more
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The AVR nuclear power facility—Progress report

Nuclear Engineering and Design, 1984
Abstract The AVR agreement was established in February 1959 by sixteen public utility companies. The objective of this association was to gain experience in the construction, operation, and especially the science, technique, and economics of the high temperature reactor (HTR).
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Engineering of nuclear power facilities for earthquake loads

Nuclear Engineering and Design, 1978
Abstract The state-of-knowledge to engineer nuclear power facilities for earthquake loads is reviewed as it was collectively presented at the fourth SMiRT Conference. All aspects of the design process is critically examined starting with the definition of ground motion.
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High Reliability Micro-Grid for a Nuclear Facility Emergency Power Supply

Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, 2018
This paper investigates the use of a high reliability micro-grid to supply emergency electrical power to a nuclear facility following loss of offsite power accident. Majority of the nuclear facilities around the world utilize diesel generators and battery banks as emergency power to back up the grid power supply.
Gerard R. Lekhema, Willem A. Cronje, Ian Korir   +2 more
openaire   +1 more source

Combined Method of Calculating Nuclear Power Facility Protection

Atomic Energy, 2018
This article is devoted to a method for calculating the radiation protection based on combined use of the Monte Carlo method and the method of characteristics. The method implements a scheme for automatic reduction of dispersion CADIS (Consistent Adjoint Driven Importance Sampling) based on the solution of a multigroup adjoint problem by the method of ...
I. R. Suslov, I. A. Lyamtsev
openaire   +1 more source

Hallam Nuclear Power Facility Electric Auxiliary-Power Systems

IEEE Transactions on Power Apparatus and Systems, 1963
This paper describes the electric auxiliary-power systems in a sodium-cooled graphite-moderated nuclear reactor (SGR). Reliability requirements and methods of achieving them are discussed, and sodium-system preheating, a requirement unique to sodium-cooled reactors, is outlined.
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U.S. DEPARTMENT OF ENERGY FACILITIES NEEDED TO ADVANCE NUCLEAR POWER

Health Physics, 2011
This talk is based upon a November 2008 report by the U.S. Department of Energy (DOE) Nuclear Energy Advisory Committee (NEAC). The report has two parts, a policy section and a technology section. Here extensive material from the Technical Subcommittee section of the NEAC report is used.
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Nuclear Power Plant Facilities and Regulatory Guides

2010
A number of nuclear power stations exist worldwide. This chapter concentrates on British, American, Canadian and European research and commercial reactors and nuclear power stations. The directory exists on the past, present and future planning for the NPS and are continuously being updated.
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Introduction to Structural Failure Modes for Nuclear Power Facilities

Journal of Energy Engineering, 1993
This introduction provides a background of the evaluation methods for earthquakes larger than design basis. Seismic probabilistic risk assessment (SPRA) and seismic margin assessment (SMA) methods are introduced to the reader. The basic parameters used to define seismic capacity for each method are explained.
John W. Reed, Orhan Gurbuz
openaire   +1 more source

Development of complex systems for automating nuclear power facilities

Atomic Energy, 2012
The basic advances made at the Dollezhal Research and Development Institute of Power Engineering in the development of the control systems and means for civilian nuclear power facilities are presented. Individual means (sensors, executing mechanisms and apparatus) and systems as a whole in the evolutionary development are reviewed in brief. The results
B. V. Lysikov, V. V. Kondratyev, M. N. Mikhailov, V. P. Potapova, S. G. Ukharov   +4 more
openaire   +1 more source