Analytical investigations of transitional operating modes of the second circuit of units at NPP with water-moderated reactors with consideration of control systems

Journal Article · Tue May 15 00:00:00 EDT 2007 · Power Technology and Engineering (Print)

DOI:https://doi.org/10.1007/S10749-007-0032-1· OSTI ID:21072451

Pikin, M A; Nesterov, Yu V ^[1]

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1. JSC 'Vserossiiskii Teplotekhnicheskii Institut' (VTI) (Russian Federation)

A mathematical model for analysis of process parameters of equipment in the second circuit of nuclear power plants is presented, and the structure of the program and principles used for analysis of the equipment are described. A mathematical model for analysis of the deaerator and steam generator is described in detail. A computational analysis of several transitional modes, which is made possible on the basis of the mathematical model in question, is also presented in this paper, and a comparison is made with test data.

• OSTI ID: 21072451
• Journal Information: Power Technology and Engineering (Print), Vol. 41, Issue 3; Other Information: DOI: 10.1007/s10749-007-0032-1; Copyright (c) 2007 Springer Science+Business Media, Inc; Country of input: International Atomic Energy Agency (IAEA); ISSN 1570-145X
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
COMPARATIVE EVALUATIONS
CONTROL SYSTEMS
EQUIPMENT
MATHEMATICAL MODELS
NUCLEAR POWER PLANTS
STEAM GENERATORS
WATER MODERATED REACTORS