Highly enriched alternatives of VVER-440 fuel assembly
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M. Bajan
Abstract
Evolution of VVER-440 fuel assembly is characterised by gradual increase of discharged fuel burn-up and prolongation of fuel cycle. Mentioned effects can be reached effectively by fuel enrichment raise and by parasitic absorption reduction. Both methods were used during VVER-440 fuel assembly optimisation, described at this paper. Enrichment interval was enlarged up to 5.95 % 235U, parasitic absorption was limited by carcass frame of the assembly. Basic characteristics of the best assembly proposals are presented and effects on equilibrium fuel cycle of VVER-440 reactor are characterised.
Kurzfassung
Die Entwicklung von WWER-440 Brennelementen ist gekennzeichnet durch die stufenweise Steigerung des Brennstoffabbrands und die Verlängerung des Brennstoffzyklus. Dies wird durch höhere Anreicherungen und durch Reduzierung unerwünschter Absorptionseffekte erzielt. In diesem Beitrag wird die Anwendung dieser Methoden zur Optimierung eines hoch angereicherten WWER-440 Brennelements beschrieben. Dabei wurde eine Anreicherung auf 5,95 % 235U erzielt und die unerwünschte Absorption wurde durch ein spezielles Design des Brennelementkastens limitiert. Die Eigenschaften dieses optimierten Brennelements und sein Einfluss auf das Zyklusgleichgewicht des Brennstoffs wird beschrieben.
References
1 Darilek, P.; Chrapciak, V.; Cudrnak, P.; Bajan, M.; Tomaskovic, J.: VVER-440 Fuel Assembly Alternatives for Higher Burn-up. 22nd AER Symposium on VVER Reactor Physics and Reactor Safety, Prague, October 1–5, 2012, pp. 233–245Suche in Google Scholar
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5 Gagarinskiy, A. A.; Saprykin, V. V.: Russia contemporary and prospective fuel cycles for VVER-440 based on new assemblies with higher uranium capacity and higher average fuel enrichment. RRC Kurchatov Institute [cit:2013-04-11]. [online]: http://library.sinap.ac.cn/db/yuanjian201102/%E5%85%A8%E6%96%87/41035581.pdfSuche in Google Scholar
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© 2014, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Editorial
- Editorial
- Technical Contributions/Fachbeiträge
- Highly enriched alternatives of VVER-440 fuel assembly
- “FULL-CORE” VVER-440 calculation benchmark
- Development of approximation method to evaluate isotopic composition of burnt fuel
- Fuel assembly burnup calculations for VVER fuel assemblies with the MONTE CARLO code SERPENT
- Solution of the CB6 benchmark on VVER-440 final disposal using the Serpent reactor physics code
- Development and verification of new nodal methods in the KIKO3DMG code
- HPLWR fine mesh core analysis
- Assessment of reactor scram effectiveness based on measured worth of separate CR groups
- Engineering factors of the macrocode MOBY-DICK
- CFD investigation of flow in the MATIS-H test facility
- Investigation of the hot-channel calculation methodology in case of shroud-less assemblies
- Assessment of the uncertainties of COBRA sub-channel calculations by using a PWR type rod bundle and the OECD NEA UAM and the PSBT benchmarks data
- Comparison analysis of effectiveness of diagnostic methods of local coolant boiling in WWER core
- Sensitivity of hydrodynamic parameters' distributions in VVER-1000 reactor pressure vessel (RPV) with respect to uncertainty of the local hydraulic resistance coefficients
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Editorial
- Editorial
- Technical Contributions/Fachbeiträge
- Highly enriched alternatives of VVER-440 fuel assembly
- “FULL-CORE” VVER-440 calculation benchmark
- Development of approximation method to evaluate isotopic composition of burnt fuel
- Fuel assembly burnup calculations for VVER fuel assemblies with the MONTE CARLO code SERPENT
- Solution of the CB6 benchmark on VVER-440 final disposal using the Serpent reactor physics code
- Development and verification of new nodal methods in the KIKO3DMG code
- HPLWR fine mesh core analysis
- Assessment of reactor scram effectiveness based on measured worth of separate CR groups
- Engineering factors of the macrocode MOBY-DICK
- CFD investigation of flow in the MATIS-H test facility
- Investigation of the hot-channel calculation methodology in case of shroud-less assemblies
- Assessment of the uncertainties of COBRA sub-channel calculations by using a PWR type rod bundle and the OECD NEA UAM and the PSBT benchmarks data
- Comparison analysis of effectiveness of diagnostic methods of local coolant boiling in WWER core
- Sensitivity of hydrodynamic parameters' distributions in VVER-1000 reactor pressure vessel (RPV) with respect to uncertainty of the local hydraulic resistance coefficients
