Published December 2001
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Experimental data and calculation studies of critical heat fluxes at local disturbances of geometry of WWER fuel assemblies
Description
The results of experiments executed in RRC 'Kurchatov Institute on the thermal-physical critical facility SVD are presented herein. The experiments modeled the drawing of two fuel rods to each other till touching WWER-1000 reactor in FA. The experimental model is a 7-rod bundle with the heated length of 1 m. The primary goal of experiments was to acquire the quantitative factors of the reduction in the critical heat fluxes as contrasted to the basic model (without disturbances of FA geometry) at the expense of local disturbance of a rod bundle geometry. As it follows from the experiment, the effect of decrease of the critical heat rate depends on combination of regime parameters and it makes 15% in the most unfavorable case (Authors)
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Additional details
Publishing Information
- Publisher
- Kiadja and KFKI Atomenergia Kutatointezet
- Imprint Place
- Budapest (Hungary)
- ISBN
- 963-372-626-3
- Imprint Title
- Proceedings of the eleventh Symposium of Atomic Energy Research
- Imprint Pagination
- 853 p.
- Journal Page Range
- p. 431-448
- Report number
- INIS-SK--2008-003
Conference
- Title
- 11. Atomic Energy Research Symposium on WWER Physics and Reactor Safety
- Dates
- 24-28 Sep 2001
- Place
- Csopak (Hungary)
INIS
- Country of Publication
- Hungary
- Country of Input or Organization
- Slovakia
- INIS RN
- 39050591
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- COMPUTER CODES; CRITICAL HEAT FLUX; DISTURBANCES; EXPERIMENTAL DATA; FUEL ASSEMBLIES; FUEL RODS; REACTORS; WWER TYPE REACTORS
- Descriptors DEC
- DATA; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; HEAT FLUX; INFORMATION; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs.; 10 figs.; 2 tabs. Imprint:Next corporations organizations: Nuclear Research Institute Rez plc, CZ-250 68 Husinec-Rez, cp.130 (Czech Republic); Forschungszentrum Rossendorf Institute of Safety Research, P.O.B. 51 01 019, D-01314 Dresden (Germany); Division 836 'Laboratory of Simulator Systems', Moscow Engineering Physics Institute, Kashirskoe shosse 31, 115 409 Moscow (RU); Budapest University of Technology and Economics, Institute of Nuclear Techniques, Budapest XI, Mueegyetem rkp. 9, 1111 (Hungary); CEA/DEN/DM2S/SERMA Saclay 91191 Gif sur Yvette (France); DSR Ingenieurgesellschaft mbH 12681 Berlin, Allee der Kosmonauten 28 (Germany); VTT Energy P.O.Box 1604, FIN-02044 VTT (Finland); Energoprojekt Praha, a.s. (CZ); Slovak University of Technology, Faculty of Electrical Engineering and Information Technology, Department of Nuclear Physics and Technology, 81219 Bratislava (Slovakia); NPP Bohunice, Jaslovske Bohunice (SK); CHEMCOMEX Praha, a.s. (CZ); University of Sofia, Faculty of Physics (Bulgaria); NPP Dukovany, 675 50 Dukovany (Czech Republic); Institute State Scientific and Technical Center for Nuclear and Radiation Safety, 35-37 Radgospna street, 03142 Kyiv-142 (Ukraine)