Published 2010 | Version v1
Miscellaneous Open

Model of cooling nuclear fuel rod in the nuclear reactor

Creators

  • 1. Department of Mechanical Engineering, University of West Bohemia, Plzen (Czech Republic)

Description

The following topics are described: Some basic requirements for nuclear fuel rods; The VVER 1000 fuel rod; Classification of the two-phase flow in the vertical tube; Type of heat transfer crisis in the vertical tube; Experimental apparatus; Model of the nuclear fuel rod and spacers; Potential of the experimental apparatus (velocity profile measurement via PIV; thermal flow field measurement by the PLIF method; cooling graph in dependence on the fuel rod temperature; comparison of the hydrodynamic properties with respect to the design features of the spacers). (P.A.)

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Additional details

Identifiers

URL
http://www.teris.cz/vver2010.htm;

Publishing Information

Imprint Pagination
17 p.
Report number
INIS-CZ--0108

Conference

Title
International topical meeting on VVER-2010 - experience and perspectives
Dates
1-3 Nov 2010
Place
Prague (Czech Republic)

INIS

Country of Publication
Czech Republic
Country of Input or Organization
Czech Republic
INIS RN
42016160
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BUBBLES; COOLING; FLUID FLOW; FUEL RODS; HEAT TRANSFER; REACTOR CORES; SPACERS; TEMPERATURE MEASUREMENT; VELOCITY; WWER TYPE REACTORS
Descriptors DEC
ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Contract/Grant/Project number
Project 101/09/P056
Notes
Presented within Section 4, Fuel, using this document as a PowerPoint presentation. The conference programme can be viewed and the contributions downloaded from the TERIS a.s. website at http://www.teris.cz/vver2010.htm. 8 figs., 5 ills.