Calculation and experimental substantiation of the WWER fuel operability at high fuel burnups
- 1. ARSRIM, Moscow (Russian Federation)
- 2. RRC 'Kurchatov Institute', Moscow (Russian Federation)
Description
In the design three-year fuel cycles of WWER-440 and two-year fuel cycles of WWER-1000 the fuel assemblies with steel spacer grids (and guiding channels in WWER-1000 FA) were used. The average burnup of spent fuel is ∼ 29 MW*day/kg. The experience of fuel operation, data of post-reactor investigations of spent fuel, results of special experiments with fresh and spent fuel, development of thermal-mechanical codes and codes of accident analysis, made it possible to substantiate in complex the increase in WWER fuel burnup, eliminate the excess conservatism in designing and operation and begin to develop new fuels cycles with advanced fuel assemblies. The paper presents the main principles, criteria and results of substantiation of WWER fuel rod availability at high burnups under normal operation conditions and of the analysis of fuel behavior in design accidents. (Authors)
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Additional details
Publishing Information
- Publisher
- Kiadja and KFKI Atomenergia Kutatointezet
- Imprint Place
- Budapest (Hungary)
- ISBN
- 963-372-622-0
- Imprint Title
- Proceedings of the Tenth Symposium of Atomic Energy Research. V. I
- Imprint Pagination
- 500 p.
- Journal Page Range
- p. 105-110
- Report number
- INIS-SK--01-008
Conference
- Title
- 10. Symposium of Atomic Energy Research on WWER Physics and Reactor Safety
- Dates
- 18-22 Sep 2000
- Place
- Moscow (Russian Federation)
INIS
- Country of Publication
- Hungary
- Country of Input or Organization
- Slovakia
- INIS RN
- 32068930
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENTS; AVAILABILITY; BEHAVIOR; BURNUP; DESIGN BASIS ACCIDENTS; FUEL ASSEMBLIES; FUEL PINS; LIMITING VALUES; REACTOR OPERATION; RODS; SPACERS; SPENT FUEL ELEMENTS; STRESS CORROSION; THERMODYNAMIC PROPERTIES; WWER-5 REACTOR
- Descriptors DEC
- ACCIDENTS; CHEMICAL REACTIONS; CORROSION; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; OPERATION; PHYSICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- 3 figs. Imprint:Next corporations organizations: Dukovany NPP, 675 50 Dukovany (CZ); Energoprojekt Praha a.s., 140 21 Praha 4 (Czech Republic); VTT Energy, Technical Research Centre of Finland, P.O.Box 1604, FIN-02044 VTT (Finland); RRC 'Kurchatov Institute', Moscow (Russian Federation); INRE-Bulgarian Academy of Science, Varna (Bulgaria); Studsvik Scandpower AS, Box 15, N-2027 Kjeller (Norway)