Published 2001
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Influence of the heat losses and accumulated heat upon the evolution of the thermohydraulic processes in the transients as applied to the ISB-WWER integral test facility
- 1. Electrogorsk Research and Engineering Centre on NPP Safety (EREC), Bezymyannaya str. 6, 142530 Electrogorsk, Moscow Region (Russian Federation)
- 2. Moscow Power Engineering Institute, Krasnokazarmennaya 14, 111250 Moscow (Russian Federation)
Description
The results of the calculational study using the RELAP5/MOD3.2 thermalhydraulic code performed on the influence of the heat losses to the ambient and the heat accumulated in the pipelines walls upon the evolution of the thermalhydraulic processes in the primary circuit of the integral test facility ISB-WWER when simulating the transients caused by the loss of the coolant are presented in the paper. (authors)
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Additional details
Identifiers
- URL
- http://www.iync.org/;
Publishing Information
- Publisher
- YDRNS Information Technology Services, Ltd.
- Imprint Place
- Obninsk (Russian Federation)
- Imprint Title
- International Youth Nuclear Congress 2000: Youth, Future, Nuclear. Proceedings and Multimedia Presentation
- Imprint Pagination
- [1000 p.]
- Journal Page Range
- [7 p.]
- Report number
- INIS-SK--2002-01
Conference
- Title
- International Youth Nuclear Congress 2000
- Acronym
- IYNC 2000
- Dates
- 9-14 Apr 2000
- Place
- Bratislava (Slovakia)
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- Slovakia
- INIS RN
- 33011245
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; DYNAMIC FUNCTION STUDIES; FLOW RATE; FUEL RODS; HEAT TRANSFER; LOSS OF COOLANT; LOSS OF FLOW; PRESSURE DEPENDENCE; PRESSURE DROP; PRIMARY COOLANT CIRCUITS; REACTOR CORE DISRUPTION; REACTOR SAFETY; REACTOR SIMULATORS; TIME DEPENDENCE; WWER-5 REACTOR
- Descriptors DEC
- ACCIDENTS; ANALOG SYSTEMS; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; FUNCTIONAL MODELS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; SIMULATION; SIMULATORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- 4 Refs, 12 figs. E-Mail: gashenko@erec.ru; kvd@npp.mpei.ac.ru; The 1"s"t CD. The publication on 2 CD-ROMs. Data in PDF and HTML format; Acrobat Reader for Windows 3.x, 95, 98, NT3.5.1, NT 4.0, 2000, MacIntosh and UNIX (SUN, HP, IRIX (SGI) and Digital UNIX) included