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Analysis of changes in the fuel component of the cost of electricity in the transition to a closed fuel cycle in nuclear power system

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Published/Copyright: August 18, 2017
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Kerntechnik
From the journal Kerntechnik Volume 82 Issue 4

Abstract

This paper presents a study of scenarios of transition to a closed fuel cycle in the system of nuclear power, built basing on resource availability requirements at the stage of full life-cycle reactors. Conventionally, there are three main scenarios for the development of nuclear energy: with VVER reactors operating in an open fuel cycle; with VVER reactors operating in a closed fuel cycle; and co-operating VVER and BN, operating in a closed fuel cycle. For the considered scenarios, a quantitative estimation of change in time of material balances were performed, including spent fuel balance, balance of plutonium, reprocessed and depleted uranium, radioactive waste, and the analysis of the fuel component of the cost of electricity.

Kurzfassung

Dieser Beitrag stellt die Ergebnisse einer Studie vor, in der Szenarien des Übergangs zu einem geschlossenen Brennstoffkreislauf in der Kernenergie untersucht werden. Diese Szenarien basieren auf der Annahme, dass die Ressource während des gesamten Lebenszyklus der Reaktoren verfügbar ist. Üblicherweise gibt es Hauptszenarien für die Entwicklung der Kernenergie: WWER-Reaktoren, die in einem offenen Brennstoffkreislauf betrieben werden; WWER-Reaktoren, die in einem geschlossenen Brennstoffkreislauf betrieben werden; und zusammen betriebene WWER- und natriumgekühlte schnelle Brutreaktoren (BN), die in einem geschlossenen Brennstoffkreislauf arbeiten. Für die betrachteten Szenarien wurde eine quantitative Berechnung der zeitabhängigen Änderung der Materialbilanzen durchgeführt, einschließlich einer Bilanzierung des abgebrannten Brennstoffs, des Plutoniums, des wiederaufbereiteten und des abgereicherten Urans, der radioaktiven Abfälle und der Analyse des Anteils der Brennstoffkosten an den Stromkosten.

References

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Received: 2017-01-30
Published Online: 2017-08-18
Published in Print: 2017-09-01

© 2017, Carl Hanser Verlag, München

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Editorial
  6. Research on the reactor physics and reactor safety of VVER reactors – AER Symposium 2016
  7. Technical Contributions/Fachbeiträge
  8. Physical startup tests for VVER-1200 of Novovoronezh NPP: advanced technique and some results
  9. Experimental study of asymmetric boron dilution at VVER-1000 of Kudankulam NPP and its simulation
  10. Study on the impact of transition from 3-batch to 4-batch loading at Loviisa NPP on the long-term decay heat and activity inventory
  11. New engineering safety factors for Loviisa NPP core calculations
  12. Development of fuel cycles with new fuel with 8.9 mm external diameter for VVER-440: Preliminary assessment of operating efficiency
  13. Investigation of circulating temperature fluctuations of the primary coolant in order to develop an enhanced MTC estimator for VVER-440 reactors
  14. Recalculating the steady state conditions of the V-1000 zero-power facility at Kurchatov Institute using Monte Carlo and nodal diffusion codes
  15. Start-up of a cold loop in a VVER-440, the 7th AER benchmark calculation with HEXTRAN-SMABRE-PORFLO
  16. Verification results of methodology for determining the weighted mean coolant temperature in the primary circuit hot legs of WWER-1000 reactor plants
  17. Advances in HELIOS2 nuclear data library
  18. ANDREA 2.2 and 2.3 – Advances in modelling of VVER cores
  19. CFD analyses of the rod bowing effect on the subchannel outlet temperature distribution
  20. A methodology for the estimation of the radiological consequences of a Loss of Coolant Accident
  21. Neutron balance as indicator of long-term resource availability in growing nuclear energy system
  22. Analysis of changes in the fuel component of the cost of electricity in the transition to a closed fuel cycle in nuclear power system
  23. Experimental and numerical thermal-hydraulics investigation of a molten salt reactor concept core
https://doi.org/10.3139/124.110816

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Editorial
  6. Research on the reactor physics and reactor safety of VVER reactors – AER Symposium 2016
  7. Technical Contributions/Fachbeiträge
  8. Physical startup tests for VVER-1200 of Novovoronezh NPP: advanced technique and some results
  9. Experimental study of asymmetric boron dilution at VVER-1000 of Kudankulam NPP and its simulation
  10. Study on the impact of transition from 3-batch to 4-batch loading at Loviisa NPP on the long-term decay heat and activity inventory
  11. New engineering safety factors for Loviisa NPP core calculations
  12. Development of fuel cycles with new fuel with 8.9 mm external diameter for VVER-440: Preliminary assessment of operating efficiency
  13. Investigation of circulating temperature fluctuations of the primary coolant in order to develop an enhanced MTC estimator for VVER-440 reactors
  14. Recalculating the steady state conditions of the V-1000 zero-power facility at Kurchatov Institute using Monte Carlo and nodal diffusion codes
  15. Start-up of a cold loop in a VVER-440, the 7th AER benchmark calculation with HEXTRAN-SMABRE-PORFLO
  16. Verification results of methodology for determining the weighted mean coolant temperature in the primary circuit hot legs of WWER-1000 reactor plants
  17. Advances in HELIOS2 nuclear data library
  18. ANDREA 2.2 and 2.3 – Advances in modelling of VVER cores
  19. CFD analyses of the rod bowing effect on the subchannel outlet temperature distribution
  20. A methodology for the estimation of the radiological consequences of a Loss of Coolant Accident
  21. Neutron balance as indicator of long-term resource availability in growing nuclear energy system
  22. Analysis of changes in the fuel component of the cost of electricity in the transition to a closed fuel cycle in nuclear power system
  23. Experimental and numerical thermal-hydraulics investigation of a molten salt reactor concept core
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