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Prospects for implementation of VVER nuclear fuel enriched above 5%

  • A. V. Ugryumov , A. B. Dolgov , A. I. Shaulskaya , Yu. M. Semchenkov , E. K. Kosourov , A. I. Osadchiy and A. M. Pavlovichev
Published/Copyright: August 27, 2019
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Kerntechnik
From the journal Kerntechnik Volume 84 Issue 4

Abstract

JSC TVEL has carried out a technical and economic study with the involvement of the National Research Centre “Kurchatov Institute” in the use of nuclear fuel enriched above the current limit of 5 wt% for VVER-1000/1200. The article presents neutronic characteristics of developed 18- and 24-month fuel cycles based on fuel enriched above 5 wt% and assessment of nuclear safety for fabrication and handling with high enriched fuel.

Kurzfassung

JSC TVEL hat eine technische und wirtschaftliche Studie unter Beteiligung des Nationalen Forschungszentrums „Kurchatov Institute“ zur Verwendung von höher angereicherten Kernbrennstoffen durchgeführt. Dabei wurde der Brennstoff über die derzeitige Grenze von 5 Gew.-% für VVER-1000/1200 angereichert. Der Artikel stellt neutronenkinetische Eigenschaften von neuen 18- und 24-monatigen Brennstoffzyklen vor, die auf Brennstoffen basieren, die über 5 Gew.-% angereichert sind, und bewertet die nukleare Sicherheit bei der Herstellung und Handhabung von höher angereichertem Brennstoff.

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References

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Received: 2019-02-14
Published Online: 2019-08-27
Published in Print: 2019-09-16

© 2019, Carl Hanser Verlag, München

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Editorial
  4. Research on the reactor physics and reactor safety of VVER reactors – AER Symposium 2018
  5. Technical Contributions/Fachbeiträge
  6. Development of CASMO5 for VVER-1000/1200 analysis and preliminary validation using critical experiments
  7. C-PORCA 7: a nodal diffusion reactor calculation code to support off-line and on-line core analysis at Paks nuclear power plant
  8. Adaptation of the gas gap simplified model in DYN3D code to new types of fuel
  9. A procedure for verification of Studsvik's spent nuclear fuel code SNF
  10. Extension of nodal diffusion solver of Ants to hexagonal geometry
  11. VVER-1000 fuel assembly model in CAD-based unstructured mesh for MCNP6
  12. Fuel cycles with PK-3+ FAs for VVER-440 reactors
  13. Prospects for implementation of VVER nuclear fuel enriched above 5%
  14. Core loading optimisation in Slovak VVER-440 reactors
  15. Statistical evaluation of C-15 cycles in Paks NPP, based on measured in-core data
  16. Optimized 18-months low-leakage core loadings for uprated VVER-1000
  17. Leningrad NPP-2 start-up loss of power test and its simulation with use of KORSAR/GP code
  18. Assessment of the fuel assembly pin-by-pin model in the KORSAR/GP code
  19. Comparative thermohydraulic analyses of VVER 1000 active core for two different construction types of assemblies
  20. Analysis of uncontrolled dilution of boric acid concentration in the reactor VVER-1000/320
  21. Applied study on optimizing the final disposal of Loviisa NPP spent fuel assemblies
  22. Criticality safety analysis for GNS IQ® – The Integrated Quiver System for damaged fuel
  23. Neutron balance in two-component nuclear energy system
https://doi.org/10.3139/124.190023

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Editorial
  4. Research on the reactor physics and reactor safety of VVER reactors – AER Symposium 2018
  5. Technical Contributions/Fachbeiträge
  6. Development of CASMO5 for VVER-1000/1200 analysis and preliminary validation using critical experiments
  7. C-PORCA 7: a nodal diffusion reactor calculation code to support off-line and on-line core analysis at Paks nuclear power plant
  8. Adaptation of the gas gap simplified model in DYN3D code to new types of fuel
  9. A procedure for verification of Studsvik's spent nuclear fuel code SNF
  10. Extension of nodal diffusion solver of Ants to hexagonal geometry
  11. VVER-1000 fuel assembly model in CAD-based unstructured mesh for MCNP6
  12. Fuel cycles with PK-3+ FAs for VVER-440 reactors
  13. Prospects for implementation of VVER nuclear fuel enriched above 5%
  14. Core loading optimisation in Slovak VVER-440 reactors
  15. Statistical evaluation of C-15 cycles in Paks NPP, based on measured in-core data
  16. Optimized 18-months low-leakage core loadings for uprated VVER-1000
  17. Leningrad NPP-2 start-up loss of power test and its simulation with use of KORSAR/GP code
  18. Assessment of the fuel assembly pin-by-pin model in the KORSAR/GP code
  19. Comparative thermohydraulic analyses of VVER 1000 active core for two different construction types of assemblies
  20. Analysis of uncontrolled dilution of boric acid concentration in the reactor VVER-1000/320
  21. Applied study on optimizing the final disposal of Loviisa NPP spent fuel assemblies
  22. Criticality safety analysis for GNS IQ® – The Integrated Quiver System for damaged fuel
  23. Neutron balance in two-component nuclear energy system
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