Efficient introduction of natural uranium and thorium into nuclear energy system
-
V. Blandinskiy
Abstract
This article describes differences between two approaches of understanding the main goal of nuclear energy system: effective plutonium consumption versus effective natural uranium and thorium consumption. Several options of sodium cooled fast reactor are considered to provide increased breeding and thorium involving into nuclear energy system.
Kurzfassung
In diesem Beitrag werden die Unterschiede zwischen den zwei Herangehensweisen zum Erreichen des Hauptziels des Brennstoffkreislaufs herausgearbeitet: Verbrauch von Plutonium oder Verbrauch von natürlichem Uran und Thorium. Dazu werden verschiedene unterstützende Optionen wie der Einsatz von natriumgekühlten schnellen Reaktoren durch verbessertes Brüten und die Berücksichtigung von Thorium betrachtet.
References
1 Physics and Safety of Transmutation Systems. A Status Report. Nuclear Energy Agency (NEA), Paris, 2006. No. 6090Search in Google Scholar
2 Shropshire, D. E.; Williams, K. A.; Boore, W. B. et al.: Advanced Fuel Cycle Cost Basis. Idaho National Laboratory (INL), Idaho, March 2008. – INL/EXT-07-12107 Rev. 1Search in Google Scholar
3 Alekseev, P. N.; Balanin, A. L.; Blandinsky, V. Yu. et al.: Prospects of subcritical molten salt reactor for minor actinides incineration in closed fuel cycle. Kerntechnik80 (2015) 38910.3139/124.110514Search in Google Scholar
4 Nuclear Energy Development in the 21st Century: Global Scenarios and Regional Trends. International Atomic Energy Agency (IAEA), Vienna, 2010. (IAEA Nuclear Energy Series No. NP-T-1.8)Search in Google Scholar
5 Waltar, Alan E.; Todd, Donald R.; Tsvetkov, Pavel V.: Fast Spectrum Reactors. Springer, 201210.1007/978-1-4419-9572-8Search in Google Scholar
© 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
