SCALE AND SERPENT TWO-GROUP CROSS-SECTION DATA GENERATION

SCALE AND SERPENT TWO-GROUP CROSS-SECTION DATA GENERATION

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,...

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Bibliographic Details
Main Authors: Ondřej Novák, Jan Frýbort, Lubomír Sklenka, Jan Rataj, Ondřej Chvála
Format: Article
Language:English
Published: Czech Technical University in Prague 2018-12-01
Series:Acta Polytechnica CTU Proceedings
Subjects:
VVER, Serpent, VVANTAGE-6, fuel cycle, burnup, SCALE, Temelin nuclear power plant, depletion calculation, homogenized cross-sections
Online Access:https://ojs.cvut.cz/ojs/index.php/APP/article/view/5225
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