In this report we present the
results of computations of the full scale reactor core with HEU (90%), MEU (36%) and LEU (19.75%) fuel. The reactor computer model for the MCU RFFI Monte
Carlo code includes all peculiarities of the core. Calculations show that a
uranium density of 3.3gU/cm3 of MEU (36%) fuel and 8.25gU/cm3 of LEU (19.75%) in WWR–M5 fuel assembly (FA) geometry is required to match
the fuel cycle length of the HEU (90%) case with the same end of cycle (EOEC) excess reactivity.
For the equilibrium fuel cycle the fuel burnup and poisoning, the fast and
thermal neutron fluxes, the reactivity worth of control rods were calculated
for the reference case with HEU (90%) FA and for the MEU and LEU FA. The relative accuracy of
this neutronic feasibility study of fuel enrichment reduction of the WWR–M
reactor in Gatchina is sufficient to start the fabrication feasibility study of
MEU (36%) WWR–M5 fuel assemblies. At the present stage of technology it seems
hardly possible to manufacture LEU (19.75%) fuel elements in WWR–M5 geometry due to too high uranium
density. Only a future R&D can solve the problem.
Yuri V. Petrov
Nuclear Physics Institute
Phone: 7 (812) 714-6096
The 2016 International RERTR Meeting (RERTR-2016) will take place in Belgium.
Stay tuned for further details.
The 2015 International RERTR Meeting (RERTR-2015) took place in Seoul, Korea on Oct. 11-14, 2015.
For more information visit RERTR-2015.