Steam oxidation of uranium mononitride in pure and reducing steam atmospheres to 1200 °C

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外文摘要：© 2021 Elsevier B.V.The present study addresses the lack of steam oxidation kinetic data for high purity uranium mononitride (UN), assesses the sensitivity of the dynamic response of UN to the density of the monolithic sample exposed to flowing steam, as well as observes the variation in the oxidation kinetic response of UN to the presence of a common fabrication contaminant, carbon. In addition, the mass spectrometry performed on the evolved gas during the reaction with steam informs the reactions thermochemistry for UN with flowing steam during a thermal ramp and during an isothermal exposure at 500 °C. It is concluded here that high purity, high density samples, (≥94% theoretical density), have a significantly delayed onset of reaction with steam compared to values previously reported, the kinetic reaction is retarded in a reducing steam atmosphere (steam + 100 ppm H2), and the reaction products are predominantly ammonia (NH3 gas) and UO2 at temperatures less than 700 °C, above which UO2+x (0.2 ≥ x ≥ 0.0) begins to form and NH3(g) dissociates.

外文关键词：

Accident tolerant fuelHigh uranium densityNuclear fuelNuclear materialsSteam oxidationUranium nitride

作者：

Sooby E.S.、Brigham B.A.、Robles G.、White J.T.、Paisner S.W.、Kardoulaki E.、Williams B.

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作者单位：

Extreme Environments Materials Laboratory Department of Physics and Astronomy University of Texas at San Antonio

Fuels Research Laboratory Materials Science and Technology Division Los Alamos National Laboratory

Radiochemistry Program Department of Chemistry and Biochemistry University of Nevada

出版年：

2022

DOI：

10.1016/j.jnucmat.2021.153487

Journal of Nuclear Materials

EISCI

ISSN：0022-3115

年,卷(期)：2022.560

参考文献量58