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...
Main Authors: | , , |
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Format: | Article |
Language: | English |
Published: |
VINCA Institute of Nuclear Sciences
2018-01-01
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Series: | Nuclear Technology and Radiation Protection |
Subjects: | |
Online Access: | http://www.doiserbia.nb.rs/img/doi/1451-3994/2018/1451-39941801024G.pdf |