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.

Downloads

Published

2018-12-14

Issue

Vol. 19 (2018): ŠIMÁNĚ 2018

Section

Articles

License

Copyright notice

Authors who publish with this journal agree to the following terms:

1. Authors retain copyright and grant the journal the right of the first publication with the work simultaneously licensed under a Creative Commons Attribution License that allows others to share the work with an acknowledgement of the work's authorship and initial publication in this journal.
2. Authors are able to enter into separate, additional contractual arrangements for the non-exclusive distribution of the journal's published version of the work (e.g., to post it to an institutional repository or to publish it in a book), with an acknowledgement of its initial publication in this journal.
3. Authors are permitted and encouraged to post their work online (e.g., in institutional repositories or on their website) prior to and during the submission process, as it can lead to productive exchanges as well as earlier and greater citation of the published work (See The Effect of Open Access).