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The Analysis of Influence of Fuel Pellet and Coolant Temperature Distributions on the VVER-1000 Active Core Characteristics

[+] Author Affiliations
A. A. Mishin

National Technical University of Ukraine “Kyiv Polytechnic Institute”, Kyiv, Ukraine

V. V. Galchenko

OJSC “KIEP”, Kyiv, Ukraine

Paper No. ICONE21-16387, pp. V006T16A036; 8 pages
  • 2013 21st International Conference on Nuclear Engineering
  • Volume 6: Beyond Design Basis Events; Student Paper Competition
  • Chengdu, China, July 29–August 2, 2013
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5583-6
  • Copyright © 2013 by ASME


The accuracy and quality of neutron-physical calculations of the active core characteristics depend heavily on the few-group constant preparation procedure. The method, based on using average in the fuel assembly fuel and coolant parameters is currently used for preparing macroscopic cross-sections. The question is what impact would considering the uneven distribution of those parameters, made on the few-group constant preparation stage exert on further analysis of the reactor facility behavior during steady-state and transients operation. The study carries out comparative analysis of the neutron-physical characteristics of the VVER-1000 core using the standard approach and using distributed in the fuel assembly fuel and coolant parameters while preparing few-group constants. It’s revealed that the fuel pellet and coolant radial temperature distributions affect the multiplication factor and temperature reactivity effect values.

Copyright © 2013 by ASME



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