Validation of the Physical Parameters of Monte Carlo Code Openmc by Unk Code for Different VVER 1200 Fuel Assemblies

Autor: H.A. Tanash, D.A.Solovyev undefined, V.G.Zimin undefined, A.A.Semenov undefined, N.V. Schukin, B. Djaroum, A.I. Al-Shamayleh
Rok vydání: 2021
Zdroj: Global Nuclear Safety. 40:62-67
ISSN: 2499-9733
2305-414X
DOI: 10.26583/gns-2021-03-06
Databáze: OpenAIRE