SCALE AND SERPENT TWO-GROUP CROSS-SECTION DATA GENERATION

Authors

  • Ondřej Novák
  • Jan Frýbort
  • Lubomír Sklenka
  • Jan Rataj
  • Ondřej Chvála

DOI:

https://doi.org/10.14311/APP.2018.19.0007

Keywords:

VVER, Serpent, VVANTAGE-6, fuel cycle, burnup, SCALE, Temelin nuclear power plant, depletion calculation, homogenized cross-sections

Abstract

In this work, VVER fuel assembly is calculated using two different codes - Serpent and SCALE. Multiplication factor and several two-group macroscopic parameters including scattering cross-section, fission cross-section, total cross-section and diffusion coefficient were studied. In addition to this, fuel isotopic composition dependency on burnup was calculated as a part of this study. Obtained data are compared and differences are discussed. Both codes provides similar results for all studied parameters.

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Published

2018-12-14

How to Cite

Novák, O., Frýbort, J., Sklenka, L., Rataj, J., & Chvála, O. (2018). SCALE AND SERPENT TWO-GROUP CROSS-SECTION DATA GENERATION. Acta Polytechnica CTU Proceedings, 19, 7–13. https://doi.org/10.14311/APP.2018.19.0007

Issue

Vol. 19 (2018): ŠIMÁNĚ 2018

Section

Articles