NEUTRONICS ANALYSIS OF VVER-1000 CORE USING AT-FCM FUEL

Using the Fully Ceramic Microencapsulated (FCM) fuel in light water reactors has multiple advantages, as it is accident tolerant because of; no hydrogen generation due to cladding interaction with steam at high temperature, better retention of fission fragments and proliferation resistant very small production transuranic elements during burnup compared standard UO2 fuel. In this study neutronics analysis AT-FCM consisting TRISO particles embedded SiC matrix performed for replacement existing VVER-1000 reactors. Standard assembly transformed Accident Tolerant (AT-FCM) based on hydraulic diameter assembly, number pins are decreased increased enrichment conserve initial fissile loading assembly. Fuel centerline temperature found be lower than reference same total power produced much higher thermal conductivity. FCM-TRISO namely Array 15 169 proposed analyzed. Pin cell, level full core calculations have been SERPENT code using implicit explicit models. modelled FCM The a use FeCrAl turns out perfect case tolerance. High terms MWd/kgHM EFPDs observed breeding Pu-239, Pu-240 Pu-241. Appreciable quantity UO 2 so remains smaller Comparatively more softening spectrum cells assemblies towards middle cycle (MOC) End Cycle (EOC), tends increase rate U-235 depletion. Very quantities plutonium isotopes U-238 BOC. performance burnable poison Gd O 3 Er turn exhibits smooth burnup. Temperature Coefficient (FTC) Moderator (MTC) negative most part however, end becomes less resonance absorbers, flux absorption .