Advanced nuclear fuel for VVER reactors. Status and operation experience
Description
The paper discusses the major VVER fuel trends, aimed at the enhancement of FAs' effectiveness and reliability, flexibility of their operating performances and fuel cycle efficiency, specifically: (i) Fuel burnup increasing is one of the major objectives during the development of improved nuclear fuel and fuel cycles. At present, the achieved fuel rod burn up is 65 MWdays/kgU. The tasks are set and the activities are carried out to achieve fuel rod burnup up to 70 MWdays/kgU and burnup of discharged batch of FAs - up to 60 MWdays/kgU. (ii) Improvement of FA rigidity enables to increase operating reliability of fuel due to gaps reducing between FAs and, as a result, the fall of peak load coefficients. FA geometric stability enables to optimize the speed of handling procedures with fuel. (iii) Increasing of uranium content of FA is aimed at extension of fuel cycles' duration. Fuel weight increase in FA is achieved both due to fuel column height extension and to changes of pellet geometrical size. (iv) Extension of FA service live satisfies the up-to-date NPP requirements for fuel cycles of various duration from 4x320 eff. days to 5x320 eff. days and 3x480 eff. days. (v) The development of new-generation FAs with increased strength characteristics has required the zirconium alloys' improvement. Advanced zirconium alloys shall provide safety and effectiveness of FA and fuel rods during long-life operation up to 40 000 eff. hours. (vi) Utilization of reprocessed uranium enables to use spent nuclear fuel in cycle and to create the partly complete fuel cycle for VVER reactors. This paper summarizes the major operating results of LTAs, which meet the modern and prospective requirements for VVER fuel, at Russian NPPs with VVER-440 and VVER-1000 reactors. (author)
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36083551.pdf
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Additional details
Publishing Information
- Publisher
- TERIS 2002
- Imprint Place
- Prague (Czech Republic)
- Imprint Title
- Proceedings of the international topical meeting VVER-2004 - experience and perspectives
- Imprint Pagination
- [1083 p.]
- Journal Page Range
- p. 578-603
- Report number
- INIS-CZ--0040
Conference
- Title
- International topical meeting VVER-2004 - experience and perspectives
- Dates
- 19-22 Oct 2004
- Place
- Prague (Czech Republic)
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 36083551
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BALAKOVO-1 REACTOR; BURNUP; BURNUP EXTENSION; DESIGN; FUEL ASSEMBLIES; FUEL RODS; KALININ-1 REACTOR; NUCLEAR FUELS; SERVICE LIFE; WWER TYPE REACTORS; ZIRCONIUM BASE ALLOYS
- Descriptors DEC
- ALLOYS; BURNUP; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; FUELS; LIFETIME; MATERIALS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS; ZIRCONIUM ALLOYS
Optional Information
- Notes
- In its original form the contribution was a PPT presentation for Microsoft PowerPoint (25 slides) completed with a textual abstract Imprint:Initially published on CD-ROM in the PPT format for Microsoft PowerPoint, DOC format for Microsoft Word, picture formats (JPG, ...), and PDF format for Adobe Acrobat. Information about the organizing bodies was obtained from sources other than the CD-ROM