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Modelling of RBMK Spent Nuclear Fuel Characteristics

[+] Author Affiliations
Arturas Smaizys, Povilas Poskas, Ernestas Narkunas

Lithuanian Energy Institute, Kaunas, Lithuania

Paper No. ICONE22-31005, pp. V004T08A018; 6 pages
doi:10.1115/ICONE22-31005
From:
  • 2014 22nd International Conference on Nuclear Engineering
  • Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory
  • Prague, Czech Republic, July 7–11, 2014
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-4594-3
  • Copyright © 2014 by ASME

abstract

After the final shutdown of Ignalina NPP, total amount of spent nuclear fuel is approximately 22 thousands of fuel assemblies. Radionuclide content and its characteristics in spent fuel are initial data for analysis of various safety related areas such as shielding, thermal analysis, radioactive releases and other processes. Experimental investigations of radionuclide content and characteristics in spent nuclear fuel are complicated and expensive, therefore numerical evaluation methods are widely used. Numerical modelling of spent RBMK fuel characteristics was performed using TRITON code from SCALE 6.1 system. Activities of fission products and actinides, gamma and neutron sources, decay heat obtained with TRITON code are compared with previous modelling results obtained using SAS2H sequence from the former SCALE 4.3 version. Some evaluated parameters are compared with published experimental data for RBMK spent nuclear fuel.

Copyright © 2014 by ASME

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