Synthesis and sintering of UN-UO2 fuel composites

JOURNAL OF NUCLEAR MATERIALS

卷:466

Article

Jaques, Brian J.^1,2  Watkins, Jennifer^1,2  Croteau, Joseph R.^1,2  Alanko, Gordon A.^1,2  Tyburska-Pueschel, Beata³  Meyer, Mitch⁴  Xu, Peng⁵  Lahoda, Edward J.⁵  Butt, Darryl P.^1,2 

[1] Boise State Univ, Dept Mat Sci & Engn, Boise, ID 83725 USA

[2] Ctr Adv Energy Studies, Idaho Falls, ID 83401 USA

[3] Univ Wisconsin, Dept Engn Phys, Madison, WI 53706 USA

[4] Idaho Natl Lab, Idaho Falls, ID 83415 USA

[5] Westinghouse Elect Co LLC, Pittsburgh, PA 15235 USA

关键词: Uranium nitride;    Composite fuel;    Nuclear fuel;   

DOI  :  10.1016/j.jnucmat.2015.06.029

来源: Elsevier

【 摘 要 】

The design and development of an economical, accident tolerant fuel (ATF) for use in the current light water reactor (LWR) fleet is highly desirable for the future of nuclear power. Uranium mononitride has been identified as an alternative fuel with higher uranium density and thermal conductivity when compared to the benchmark, UO2, which could also provide significant economic benefits. However, UN by itself reacts with water at reactor operating temperatures. In order to reduce its reactivity, the addition of UO2 to UN has been suggested. In order to avoid carbon impurities, UN was synthesized from elemental uranium using a hydride-dehydride-nitride thermal synthesis route prior to mixing with up to 10 wt% UO2 in a planetary ball mill. UN and UN UO2 composite pellets were sintered in Ar - (0-1 at %) N-2 to study the effects of nitrogen concentration on the evolved phases and microstructure. UN and UN-UO2 composite pellets were also sintered in Ar - 100 ppm N-2 to assess the effects of temperature (1700-2000 degrees C) on the final grain morphology and phase concentration. (C) 2015 Published by Elsevier B.V.

【 授权许可】

Free