VVER-440 with inert matrix fuel – viable direction to sustainability
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P. Dařílek
Abstract
Reutilisation of fissile nuclides after reprocessing in light water reactor VVER-440 with inert matrix fuel (IMF) is analysed. Development of transmutation combined fuel assembly, containing two pin types – with metal molybdenum + PuO2 mixture and with classical UO2 – is described. Static characteristics of five-year VVER-440 fuel cycle with IMF are given. Results of control rod ejection accident analysis are presented. Necessary improvements of transmutation combined fuel assembly with IMF for the reactor VVER-440 are mentioned.
Kurzfassung
Es wird die Verwendung von wiederaufbereitetem Spaltmaterial in WWER-440 Reaktoren mit einer inerten Brennstoffmatrix analysiert. Dabei wird die Entwicklung eines Brennelementes, das Brennstäbe aus einer Mischung aus metallischem Molybdän und Pu02 und klassische U02-Brennstäbe enthält, beschrieben. Es werden stationäre Daten eines fünfjährigen Zyklus eines solchen Kerns mit inerter Brennstoffmatrix in einem WWER-440 vorgestellt. Auch Ergebnisse der Untersuchung der Auswirkungen des Ereignisses Auswurf eines Steuerstabes in einem solchen Kern werden beschrieben. Abschlieβend werden daraus abgeleitete Verbesserungsvorschläge für die Auslegung solcher Brennelemente für WWER-440 diskutiert.
References
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© 2012, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries/Kurzfassungen
- Editorial
- Research on the reactor physics and reactor safety of VVER reactors – Selected contributions to the XXIst Symposium of the Atomic Energy Research organization
- Technical Contributions/Fachbeiträge
- Development of multi-group spectral code TVS-M
- Qualification of the APOLLO2 lattice physics code of the NURISP platform for VVER hexagonal lattices
- The simplified P3 approach on a trigonal geometry of the nodal reactor code DYN3D
- An analytical solution for the consideration of the effect of adjacent fuel assemblies; extension to VVER-440 type fuel assemblies
- Studies on boiling water reactor design with reduced moderation and analysis of reactivity accidents using the code DYN3D-MG
- Simulations of RUTA-70 reactor with CERMET fuel using DYN3D/ATHLET and DYN3D/RELAP5 coupled codes
- Analysis of coolant flow in central tube of VVER-440 fuel assemblies
- Effect of spacer grid mixing vanes on coolant outlet temperature distribution
- Study on severe accidents and countermeasures for VVER-1000 reactors using the integral code ASTEC
- Assessment of spectral history influence on PWR and WWER core
- New practice for the evaluation of rod efficiency measurement by rod drop at the NPP Paks
- Comparison of square and hexagonal fuel lattices for high conversion PWRs
- VVER-440 with inert matrix fuel – viable direction to sustainability
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries/Kurzfassungen
- Editorial
- Research on the reactor physics and reactor safety of VVER reactors – Selected contributions to the XXIst Symposium of the Atomic Energy Research organization
- Technical Contributions/Fachbeiträge
- Development of multi-group spectral code TVS-M
- Qualification of the APOLLO2 lattice physics code of the NURISP platform for VVER hexagonal lattices
- The simplified P3 approach on a trigonal geometry of the nodal reactor code DYN3D
- An analytical solution for the consideration of the effect of adjacent fuel assemblies; extension to VVER-440 type fuel assemblies
- Studies on boiling water reactor design with reduced moderation and analysis of reactivity accidents using the code DYN3D-MG
- Simulations of RUTA-70 reactor with CERMET fuel using DYN3D/ATHLET and DYN3D/RELAP5 coupled codes
- Analysis of coolant flow in central tube of VVER-440 fuel assemblies
- Effect of spacer grid mixing vanes on coolant outlet temperature distribution
- Study on severe accidents and countermeasures for VVER-1000 reactors using the integral code ASTEC
- Assessment of spectral history influence on PWR and WWER core
- New practice for the evaluation of rod efficiency measurement by rod drop at the NPP Paks
- Comparison of square and hexagonal fuel lattices for high conversion PWRs
- VVER-440 with inert matrix fuel – viable direction to sustainability
