TEM characterization of irradiated U-7Mo/Mg dispersion fuel

JOURNAL OF NUCLEAR MATERIALS

卷:494

Article

Gan, J.¹  Keiser, D. D., Jr.¹  Miller, B. D.¹  Jue, J. F.¹  Robinson, A. B.¹  Madden, J.¹ 

[1] Idaho Natl Lab, Adv PIE & Characterizat Div, POB 1625, Idaho Falls, ID 83415 USA

关键词: Dispersion fuel;    TEM;    Mg matrix;    U-7Mo;    Fission;    Microstructure;   

DOI  :  10.1016/j.jnucmat.2017.07.030

来源: Elsevier

【 摘 要 】

This paper presents the results of transmission electron microscopy (TEM) characterization on neutron-irradiated samples taken from the low-flux and high-flux sides of the same fuel plate with U-7Mo fuel particles dispersed in Mg matrix with aluminum alloy Al6061 as cladding material that was irradiated edge-on to the core in the Advanced Test Reactor. The corresponding local fission density and fission rate of the fuel particles and the average fuel-plate centerline temperature for the low-flux and high-flux samples are estimated to be 3.7 x 10(21) f/cm(3), 7.4 x 10(14) f/cm(3)/s and 123 degrees C, and 5.5 x 10(21) f/cm(3), 11.0 x 10(14) f/cm(3)/s and 158 degrees C, respectively. Complex interaction layers developed at the Al-Mg interface, consisting of Al3Mg2 and Al12Mg17 along with precipitates of MgO, Mg2Si and FeAl5.3. No interaction between Mg matrix and U-Mo fuel particle was identified. For the U-Mo fuel particles, at low fission density, small elongated bubbles wrapped around the clean areas with a fission gas bubble superlattice, which suggests that bubble coalescence is an important mechanism for converting the fission gas bubble superlattice to large bubbles. At high fission density, no bubbles or porosity were observed in the Mg matrix, and pockets of residual fission gas bubble superlattice were observed in the U-Mo fuel particle interior. Published by Elsevier B.V.

【 授权许可】

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