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BEHAVIORS OF MOLYBDENUM IN UO<sub>2</sub> FUEL MATRIX
BEHAVIORS OF MOLYBDENUM IN UO2 FUEL MATRIX
Nuclear Engineering and Technology. 2011. Jun, 43(3): 309-316
  • Published : June 25, 2011
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Ha, Yeong-Keong
Kim, Jong-Goo
Park, Yang-Soon
Park, Soon-Dal
Song, Kyu-Seok

Abstract
Molybdenum is the most abundant fission product since its fission yield is equivalent to that of xenon, and it has a very special role in the chemistry of nuclear fuel because it influences the oxygen potential of $UO_2$ fuel. In this study, the distribution of molybdenum in spent $UO_2$ fuel specimens with 33.3, 41.0 and 57.6 GWd/tU burnup was measured by a LA-ICP-MS system and the reproducibility of the measured data was obtained. The Mo distribution was almost constant along the radius of a fuel except an increase at the periphery of the fuel. It showed a drop in reproducibility with relatively high deviation of measured values for the highest burnup fuel. To explain this, the state of molybdenum in a $UO_2$ matrix and its effect on the oxidation behavior of $UO_2$ were investigated. The low reproducibility was explained by the segregation of molybdenum, and the inhibition of oxidation by the molybdenum was also observed.
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