Stable In-reactor Performance of Centrifugally Atomized U-10wt.%Mo Dispersion Fuel at Low Temperature

Kihwan Kim, Hee-Jun Kwon, Jong-Man Park,Yoon-Sang Lee,Chang-Kyu Kim

Nuclear Engineering and Technology(2001)

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摘要
In order to examine the in-reactor performance of very-high-density dispersion fuels for high flux performance research reactors, U-l0wt.%Mo microplates containing centrifugally atomized powder were irradiated at low temperature. The U-l0wt.%Mo dispersion fuels show stable in- reactor irradiation behaviors even at high burn-up, similar to USi dispersion fuels. The atomized U-l0wt.%Mo fuel particles have a fine and a relatively uniform fission gas bubble size distribution. Moreover, only one of third of the area of the atomized fuel cross-sections at 70a1.% burn-up shows fission gas bubble-free zones, This appears to be the result of segregation into high Mo and low Mo.
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