Pu dissolution yield of a spent SFR MOX fuel as a function of axial position in the reactor (PHENIX NESTOR-3 tests)

摘要

Three dissolution experiments were carried out on 30mm long pieces of irradiated materials after shearing threedistinct 120 mm sections of a (U,Pu)O2 fissile NESTOR-3pin (bottom, middle i.e. full-flux zone, and upper).Dissolution experiments were performed out in boilingnitric acid (8 M) for 6 hours to produce a feed solutionconcentrated to about 180 g/L of HM.The results showed that the undissolved Pu rate isbetween 0.09% for the full-flux zone portion and 0.21% forthe upper zone, the least irradiated. These results are inaccordance with the feedback on SFR fuel treatment, i.e. anundissolved Pu rate value on average close to 0.1%.