Kizub P.A., Blokhin A.I., Blokhin P.A.
Nuclear Safety Institute of the Russian Academy of Sciences, Moscow, Russia
– Junior Researcher. Contacts: B. Tulskaya Str. 52, Moscow 115191, Russia. Tel.: +7 (495) 955-23-35; e-mail:
– Leading Researcher, Cand. Sci. (Phys.-Math.).
– Researcher, Cand. Sci. (Tech.).
A preliminary criticality analysis for novel pyrochemical apparatuses for the reprocessing of mixed uranium-plutonium nitride spent nuclear fuel from the BREST-OD-300 reactor, was performed. High-temperature processing apparatuses, “metallization” electrolyzer, refinery remelting apparatus, refining electrolyzer, and “soft” chlorination apparatus are considered in this work. Computational models of apparatuses for two neutron radiation transport codes (MCU-FR and MCNP) were developed and calculations for criticality were completed using the Monte Carlo method.
The criticality analysis was performed for different loads of fissile material into the apparatuses including overloading conditions. Various emergency situations were considered: cooldown to room temperature, fission material spillages, increasing of electrolyte in “metallization” apparatus, water ingress into the chamber of the refinery remelting apparatus. It was revealed that for all the considered computational models nuclear safety rules are satisfied. The distributions of fission neutrons for “metallization” electrolyzer apparatus were analyzed for different spillage height to determine that the system is not loosely-coupled and doesn't require additional analysis of calculated functionals convergence.
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