Detailed measurements of local thickness changes for U-7Mo dispersion fuel plates with Al-3.5Si matrix after irradiation at different powers in the RERTR-9B experiment

JOURNAL OF NUCLEAR MATERIALS

卷:494

Article

Keiser, Dennis D., Jr.¹  Williams, Walter¹  Robinson, Adam¹  Wachs, Dan¹  Moore, Glenn¹  Crawford, Doug¹ 

[1] Idaho Natl Lab, Nucl Fuels & Mat Div, POB 1625, Idaho Falls, ID 83415 USA

关键词: Low-enriched uranium fuel;    Uranium molybdenum alloy;    Dispersion fuel;    Nuclear fuel;    Swelling;    Plate fuel;    Research reactors;   

DOI  :  10.1016/j.jnucmat.2017.07.047

来源: Elsevier

【 摘 要 】

The Materials Management and Minimization program is developing fuel designs to replace highly enriched fuel with fuels of low enrichment. Swelling is an important irradiation behavior that needs to be well understood. Data from high resolution thickness measurements performed on U-7Mo dispersion fuel plates with Al-Si alloy matrices that were irradiated at high power is sparse. This paper reports the results of detailed thickness measurements performed on two dispersion fuel plates that were irradiated at relatively high power to high fission densities in the Advanced Test Reactor in the same RERTR-9B experiment. Both plates were irradiated to similar fission densities, but one was irradiated at a higher power than the other. The goal of this work is to identify any differences in the swelling behavior when fuel plates are irradiated at different powers to the same fission densities. Based on the results of detailed thickness measurments, more swelling occurs when a U-7Mo dispersion fuel with Al-3.5Si matrix is irradiated to a high fission density at high power compared to one irradiated at a lower power to high fission density. (C) 2017 Elsevier B.V. All rights reserved.

【 授权许可】

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