At the same time, TVEL continues development of the 2nd-generation fuel rods for the BREST-OD-300 with a higher burnout level, which will be used when MNUP fabrication will shift to the re-fabrication stage (meaning that irradiated fuel of the 1st load after irradiation and reprocessing will be used for fresh fuel fabrication).
Mikhail Skupov, Deputy Director General of the Bochvar Institute, said:
- Pilot fuel assemblies with nitride fuel have been irradiated in the BN-600 reactor at the Beloyarsk NPP since 2014
- Though the sufficient validated fuel burnout for the BREST initial load is 6%, in the course of the testing we have already achieved the 9% level These results give us the grounds for the fuel rod endurance tests with 9-10% burnout
- The research results related to nitride fuel for the BREST reactor will significantly accelerate fuel development for the nitride core version of the next generation BN-1200M fast reactor
- In 2022, experimental fuel assemblies with fuel rods of BN-1200M type are scheduled to be loaded in the BN-600 for endurance tests
In February 2021, Rostechnadzor issued a license to for construction of BREST-OD-300, the world's 1st power unit with a lead-cooled fast neutron reactor.