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Anode processes on Pt and ceramic anodes in chloride and oxide-chloride melts
A.R. Mullabaev,V.A. Kovrov,A.S. Kholkina,Yu.P. Zaikov 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.3
Platinum anodes are widely used for metal oxides reduction in LiCleLi2O, however high-cost and lowcorrosionresistance hinder their implementation. NiOeLi2O ceramics is an alternative corrosion resistantanode material. Anode processes on platinum and NiOeLi2O ceramics were studied in (80 mol.%)LiCl-(20mol.%)KCl and (80 mol.%)LiCl-(20 mol.%)KCleLi2O melts by cyclic voltammetry, potentiostatic andgalvanostatic electrolysis. Experiments performed in the LiCleKCl melt without Li2O illustrate that a Ptanode dissolution causes the Pt2þ ions formation at 3.14 V and 550 С and at 3.04 V and 650оС. A twostagePt oxidation was observed in the melts with the Li2O at 2.40 ÷ 2.43 V, which resulted in theLi2PtO3 formation. Oxygen current efficiency of the Pt anode at 2.8 V and 650 С reached about 96%. Theanode process on the NiOeLi2O electrode in the LiCleKCl melt without Li2O proceeds at the potentialsmore positive than 3.1 V and results in the electrochemical decomposition of ceramic electrode to NiOand O2. Oxygen current efficiency on NiOeLi2O is close to 100%. The NiOeLi2O ceramic anode demonstratedgood electrochemical characteristics during the galvanostatic electrolysis at 0.25 A/cm2 for 35 hand may be successfully used for pyrochemical treating of spent nuclear fuel.
Kizub P.A.,Blokhin A.I.,Blokhin P.A.,Mitenkova E.F.,Mosunova N.A.,Kovrov V.A.,Shishkin A.V.,Zaikov Yu.P.,Rakhmanova O.R. 한국원자력학회 2023 Nuclear Engineering and Technology Vol.55 No.3
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. Hightemperature 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, in particular, those associated with 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.