Computational benchmark for fuel assembly of VVER-1000 using the Monte Carlo Serpent code

The use of a new Monte Carlo Serpent code for the calculation of water-cooled reactors is presented and a calculation scheme of the fuel assembly for VVER-1000 reactors developed. The calculation of neutron-physical characteristics for the fuel assembly of VVER-1000 is carried out for di...

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Bibliographic Details
Main Authors: Galchenko Vitaliy V., Shlapak Ihor, Gulik Volodymyr
Format: Article
Language:English
Published: VINCA Institute of Nuclear Sciences 2018-01-01
Series:Nuclear Technology and Radiation Protection
Subjects:
Online Access:http://www.doiserbia.nb.rs/img/doi/1451-3994/2018/1451-39941801024G.pdf