作者: Ali Traboulsi , Johan Vandenborre , Guillaume Blain , Bernard Humbert , Ferid Haddad
DOI: 10.1016/J.JNUCMAT.2015.10.061
关键词: Uranium dioxide 、 Phase (matter) 、 Grain boundary 、 Corrosion 、 Irradiation 、 Chemistry 、 Uranium 、 Inorganic chemistry 、 Spectrophotometry 、 Radiolysis 、 Nuclear chemistry
摘要: Abstract The short-range (few μm in water) of the α-emitting from spent fuel involves that radiolytic corrosion this kind sample occurs at solid/solution interface. In order to establish role localization H 2 O species produced by He 2+ particle beam water surface, we perform UO experiment with different distance between production area and surface. Then, work, particles oxidative 4 radiolysis was investigated open air atmosphere. dose rate, grain boundaries present on surface were investigated. situ (during irradiation) characterization solid analysis quantification uranium released into solution during irradiation. Characterization particles, volume, realized Raman spectroscopy. UV–vis spectrophotometry used monitor parallel soluble quantified inductively coupled plasma mass spectrometry. During irradiation ultra-pure contact metastudtite phase formed indicating an oxidation process radiolysis. This occurred essentially accompanied migration (U(VI)) irradiated solution. Closer formation, higher occurs, whereas rate had no effect it. Simultaneously, closer formation lower concentration measured Moreover, only secondary whatever conditions. One hypothesis proposed work is may undergo a dismutation reaction leading OH at