Scanning Electron Microscopy Analysis of Fuel/Matrix Interaction Layers in Highly-Irradiated U–Mo Dispersion Fuel Plates with Al and Al–Si Alloy Matrices

Dennis D. Keiser; JAN-FONG JUE; BRANDON D. MILLER; JIAN GAN; ADAM B. ROBINSON; PAVEL MEDVEDEV; JAMES MADDEN; DAN WACHS; MITCH MEYER

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자료유형: 학술저널

저자정보: Dennis D. Keiser JAN-FONG JUE BRANDON D. MILLER JIAN GAN ADAM B. ROBINSON PAVEL MEDVEDEV JAMES MADDEN DAN WACHS MITCH MEYER

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제46권 제2호

발행연도: 2014.1

수록면: 147 - 158 (12page)

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In order to investigate how the microstructure of fuel/matrix-interaction (FMI) layers change during irradiation, differentU–7Mo dispersion fuel plates have been irradiated to high fission density and then characterized using scanning electronmicroscopy (SEM). Specifially, samples from irradiated U–7Mo dispersion fuel elements with pure Al, Al–2Si and AA4043(~4.5 wt.%Si) matrices were SEM characterized using polished samples and samples that were prepared with a focused ionbeam (FIB). Features not observable for the polished samples could be captured in SEM images taken of the FIB samples. Forthe Al matrix sample, a relatively large FMI layer develops, with enrichment of Xe at the FMI layer/Al matrix interface andevidence of debonding. Overall, a significant penetration of Si from the FMI layer into the U–7Mo fuel was observed forsamples with Si in the Al matrix, which resulted in a change of the size (larger) and shape (round) of the fission gas bubbles. Additionally, solid fission product phases were observed to nucleate and grow within these bubbles. These changes in thelocalized regions of the microstructure of the U–7Mo may contribute to changes observed in the macroscopic swelling of fuelplates with Al–Si matrices.

#Electron Microscopy #Nuclear Fuel #Research Reactor #Uranium Molybdenum Alloy #Microstructure

참고문헌 (22)

참고문헌 신청

A. Leenaers / 2004 / Post-Irradiation Examination of Uranium?7 wt% Moloybdenum Atomized Disersion Fuel / J. Nucl. Mater 335 : 39 ~ 47

A. Leenaers / 2013 / Microstructural Evolution of U(Mo)?Al(Si) Dispersion Fuel Under Irradiation?Destructive Analyses of the LEONIDAS E-FUTURE Plates / J. Nucl. Mater 441 :

Aleksey L. Izhutov / 2013 / Comparative Analysis of Structural Changes in U-Mo Dispersed Fuel of Full-size Fuel Elements and Mini-rods Irradiated in the MIR Reactor / Nuclea

Bo Yao / 2011 / Microstructure characterization of as-fabricated and 475°C annealed U?7 wt.% Mo dispersion fuel in Al?Si alloy matrix / J. Alloys Compounds 509 : 9487 ~ 9496

Brandon D. Miller / 2012 / Advantages and Disadvantages of Using a Focused Ion Beam to Prepare TEM Samples from Irradiated U?10Mo Monolithic Nuclear Fuel / J. Nucl. Mater 424