Bubble formation and Kr distribution in Kr-irradiated UO 2

Abstract In situ and ex situ transmission electron microscopy observation of small Kr bubbles in both single-crystal and polycrystalline UO 2 were conducted to understand the inert gas bubble behavior in oxide nuclear fuel. The bubble size and volume swelling are shown as weak functions of ion dose but strongly depend on the temperature. The Kr bubble formation at room temperature was observed for the first time. The depth profiles of implanted Kr determined by atom probe tomography are in good agreement with the calculated profiles by SRIM, but the measured concentration of Kr is about 1/4 of the calculated concentration. This difference is mainly due to low solubility of Kr in UO 2 matrix and high release of Kr from sample surface under irradiation.