Neutron fluxes measurements and calculations in WWER-SM reactor of INP AS RUZ

Full text: In the work results of neutron flux density determination in the reactor active zone for vertical and horizontal channels after the complete replacement of IRT-3M type fuel assemblies with 36 percent enrichment U 235 are presented. Calculations for the optimal configuration finding of the FA disposition in the reactor active zone with the aim of obtaining of the uranium fuel minimal expense and the maximal power at the minimal factor of volumetric non-uniformity were carried out. Accordance of experimental data with results of calculations will allow us to use these results for the choice of the optimal regimes of the exploitation of reactor to provide its safety at the researches