Title

Synthesis and Sintering of UN-UO2 Fuel Composites

Document Type

Article

Publication Date

11-2015

Abstract

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 %) N2 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 N2 to assess the effects of temperature (1700‒2000 ˚C) on the final grain morphology and phase concentration.

Comments

For a complete list of authors, please see article.