Effects of irradiation on the interface between U-Mo and zirconium diffusion barrier

JOURNAL OF NUCLEAR MATERIALS

卷:499

Article

Jue, Jan-Fong¹  Keiser, Dennis D., Jr.¹  Miller, Brandon D.¹  Madden, James W.¹  Robinson, Adam B.¹  Rabin, Barry H.¹ 

[1] Idaho Natl Lab, 1955 N Fremont Ave, Idaho Falls, ID 83415 USA

关键词: Monolithic;    Diffusion barrier;    Zirconium;    U-Mo;    Nuclear fuel;   

DOI  :  10.1016/j.jnucmat.2017.10.072

来源: Elsevier

【 摘 要 】

Irradiated fuel plates were characterized by microscopy that focused on the interface between U-Mo and Zr. Before irradiation, there were three major sub-layers identified in the U-Mo/Zr interface, namely, UZr2, Mo2Zr, and U with low Mo. The typical total thickness of this U-Mo/Zr interaction is 2-3 mu m. The UZr2 sub-layer formed during fuel plate fabrication remains stable after irradiation, without large bubbles/porosity accumulation. However, this sub-layer becomes increasingly discontinuous as burnup increases. The low-Mo sub-layer exhibits numerous sub-micron bubbles/porosity at low burnup. Larger, interconnected porosity in this sub-layer was observed in a medium-burnup fuel specimen. However, at higher burnup, regions with the extra-large bubbles/porosity (i.e., larger than 5 mu m) were observed in the U-Mo fuel foil at least 5 mu m away from the original location of this sub-layer. The mechanism for the formation of the extra-large bubbles/porosity is still unclear at this time. In general, the U-Mo/Zr interface in monolithic U-Mo fuels is relatively stable after irradiation. No large detrimental defects, such as large interfacial bubbles or cracks/delamination, were observed in the fuel plates characterized. (C) 2017 Elsevier B.V. All rights reserved.

【 授权许可】

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