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...
Gorde:
| Egile Nagusiak: | , , |
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| Formatua: | Artigo |
| Hizkuntza: | Inglês |
| Argitaratua: |
VINCA Institute of Nuclear Sciences
2018-01-01
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| Saila: | Nuclear Technology and Radiation Protection |
| Gaiak: | |
| Sarrera elektronikoa: | http://www.doiserbia.nb.rs/img/doi/1451-3994/2018/1451-39941801024G.pdf |
| Etiketak: |
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