Economical aspects of multiple plutonium and uranium recycling in VVER reactors
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P. N. Alekseev
Abstract
The basic strategy of Russian Nuclear Energy development is the formation of the closed fuel cycle based on fast breeder and thermal reactors, as well as the solution of problems of spent nuclear fuel accumulation and availability of resources. Three options of multiple Pu and U recycling in VVER reactors are considered in this work. Comparison of MOX and REMIX fuel recycling approaches for the closed fuel cycle involving thermal reactors is presented. REMIX fuel is supposed to be fabricated from non-separated mixture of uranium and plutonium obtained in spent fuel reprocessing with further makeup by enriched U. These options make it possible to recycle several times the total amount of Pu and U obtained from spent fuel. The main difference is the full or partial fuel loading of the core by assemblies with recycled Pu. The third option presents the concept of heterogeneous arrangement of fuel pins made of enriched uranium and MOX in one fuel assembly. It should be noted that fabrication of all fuel assemblies with Pu requires the use of expensive manufacturing technology. These three options of core loading can be balanced with respect to maximum Pu and U involvement in the fuel cycle. Various physical and economical aspects of Pu and U multiple recycling for selected options are considered in this work.
Kurzfassung
Die Grundstrategie der russischen Kernenergieentwicklung ist die Bildung eines geschlossenen nuklearen Brennstoffkreislaufs auf Basis von schnellen Brut- und thermischen Reaktoren sowie die Lösung der Fragen der Akkumulation abgebrannter Brennelemente und der Verfügbarkeit von Ressourcen. Drei Optionen für das Mehrfachrecycling von Pu und U in WWER-Reaktoren werden in dieser Arbeit betrachtet. Als erstes werden MOX- und REMIX-Brennstoffrecycling-Ansätze für den geschlossenen Brennstoffkreislauf verglichen, bei denen thermischen Reaktoren beteiligt sind. REMIX-Brennstoff soll dabei aus einer Mischung aus Uran und Plutonium, wie sie bei der Wiederaufarbeitung abgebrannter Brennelemente anfällt, mit Zusatz von angereichertem U hergestellt werden. Diese beiden Optionen ermöglichen es, mehrmals die aus abgebrannten Brennelementen gewonnene Gesamtmenge von Pu und U zu recyceln. Der Hauptunterschied ist dann die vollständige oder teilweise Beladung des Kerns mit Brennelementen aus Recycling-Pu. Bei der dritten Option werden Brennstäbe aus angereichertem Uran und MOX-Brennstäbe heterogen in einem Brennelement gemischt. Allen Verfahren gemeinsam ist, dass die Herstellung aller Brennelemente mit Pu den Einsatz teurer Herstellungstechnologie erfordert. Eine Bilanzierung dieser drei Optionen der Kernbeladung im Hinblick auf die maximale Pu und U Einbindung im gesamten Brennstoffkreislauf wird ebenso im Beitrag gegeben wie die Betrachtung verschiedener physikalischer und wirtschaftlicher Aspekte von Pu und U beim Mehrfach-Recycling.
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© 2016, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Editorial
- Research on the reactor physics and reactor safety of VVER reactors – AER Symposium 2015
- Technical Contributions/Fachbeiträge
- Monte-Carlo code calculation of 3D reactor core model with usage of burnt fuel isotopic compositions, obtained by engineering codes
- Xenon instability study of large core Monte Carlo calculations
- Error detection in core loading in the condition of asymmetrical distribution of power
- New models in VERONA 7.0 system
- Methodology for determining of the weighted mean coolant temperature in the primary circuit hot legs of WWER-1000 reactor plants
- Verification of three-dimensional neutron kinetics model of TRAP-KS code regarding reactivity variations
- Aspects of using a best-estimate approach for VVER safety analysis in reactivity initiated accidents
- Qualification of coupled 3D neutron kinetic/thermal hydraulic code systems by the calculation of a VVER-440 benchmark – re-connection of an isolated loop
- Uncertainties of the KIKO3D-ATHLET calculations using the Kalinin-3 benchmark (Phase II) data
- Coupled code analysis of uncertainty and sensitivity of Kalinin-3 benchmark
- Efficient introduction of natural uranium and thorium into nuclear energy system
- Economical aspects of multiple plutonium and uranium recycling in VVER reactors
- Neutronic analysis of absorbing materials for the control rod system in reactor ALLEGRO
- Uncertainty analysis and flow measurements in an experimental mock-up of a molten salt reactor concept
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Editorial
- Research on the reactor physics and reactor safety of VVER reactors – AER Symposium 2015
- Technical Contributions/Fachbeiträge
- Monte-Carlo code calculation of 3D reactor core model with usage of burnt fuel isotopic compositions, obtained by engineering codes
- Xenon instability study of large core Monte Carlo calculations
- Error detection in core loading in the condition of asymmetrical distribution of power
- New models in VERONA 7.0 system
- Methodology for determining of the weighted mean coolant temperature in the primary circuit hot legs of WWER-1000 reactor plants
- Verification of three-dimensional neutron kinetics model of TRAP-KS code regarding reactivity variations
- Aspects of using a best-estimate approach for VVER safety analysis in reactivity initiated accidents
- Qualification of coupled 3D neutron kinetic/thermal hydraulic code systems by the calculation of a VVER-440 benchmark – re-connection of an isolated loop
- Uncertainties of the KIKO3D-ATHLET calculations using the Kalinin-3 benchmark (Phase II) data
- Coupled code analysis of uncertainty and sensitivity of Kalinin-3 benchmark
- Efficient introduction of natural uranium and thorium into nuclear energy system
- Economical aspects of multiple plutonium and uranium recycling in VVER reactors
- Neutronic analysis of absorbing materials for the control rod system in reactor ALLEGRO
- Uncertainty analysis and flow measurements in an experimental mock-up of a molten salt reactor concept
