par Gregori, Giacomo 
;Doneux, Thomas ;Lim, Jun
Référence Journal of the Electrochemical Society, 170, 061505
Publication Publié, 2023-06-16
;Doneux, Thomas ;Lim, JunRéférence Journal of the Electrochemical Society, 170, 061505
Publication Publié, 2023-06-16
Article révisé par les pairs
| Résumé : | The use of liquid Pb-Bi eutectic alloy (LBE) as primary coolant and spallation target in Lead-cooled Fast Reactors (LFRs) and Accelerator Driven Systems (ADSs) presents a corrosion challenge, as structural materials can release impurities, such as Fe, Cr, Ni and Co, into the coolant. These corrosion product impurities can react with dissolved oxygen, resulting in the formation of solid oxide particles that can block the critical flow channels in the core or heat-exchanger, compromising the safety of the reactor. Of particular concern is the additional radiological risk posed by cobalt, which can undergo neutron capture and be transmuted into the γ-emitter (_27^60)Co. Therefore, it is essential to accurate assess the cobalt oxide solubility product and the cobalt solubility limit. In this work, we characterized the Co-O-LBE system through an electrochemical method that involved the coulometric titration of oxygen. By analyzing the oxygen evolution during CoO formation in LBE while titrating oxygen, we derived the following CoO solubility product (Ksp) and Co solubility (SCo) thermal laws:log_10〖(K_sp)=1.22-7386/T_([K]) 〗 (673‒778 K)log_10〖(S_(Co [wt.%] ))=0.64-2233/T_([K]) 〗 (673‒778 K) |
