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Materials in Nuclear Energy Systems (MiNES 2023)
December 10–14, 2023
New Orleans, LA|New Orleans Marriott
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From the pages of Nuclear News: Industry update November 2023
Here is a recap of industry happenings from the recent past:
Centrus-Oklo partnership expands
Oklo, a California-based developer of next-generation fission reactors, has expanded its partnership with Centrus Energy, a Maryland-based supplier of nuclear fuel and services. The two companies have been cooperating since 2021 on the development of Centrus’s American Centrifuge Plant in Piketon, Ohio, to produce high-assay low-enriched uranium (HALEU) fuel. According to the companies’ new memorandum of understanding, Centrus will manufacture certain components for Oklo’s Aurora “powerhouse” reactor, a fast neutron reactor designed to generate up to 15 MW of power and operate for at least 10 years without refueling. The Aurora is also designed to produce usable heat. Centrus also has agreed to purchase electricity generated by the Aurora reactors, while Oklo has agreed to purchase HALEU fuel from the Piketon facility. The facility is expected to begin fuel production before the end of the year.
Dawn E. Janney, Steven L. Hayes
Nuclear Technology | Volume 203 | Number 2 | August 2018 | Pages 109-128
Critical Review | doi.org/10.1080/00295450.2018.1435137
Articles are hosted by Taylor and Francis Online.
More than 14 000 U-10Zr fuel rods (alloys of U with 10 wt% Zr) were irradiated in the Experimental Breeder Reactor II and Fast Flux Test Facility, with some irradiated to burnups of almost 20 at. %. However, very little information about properties of unirradiated U-10Zr alloys is available. These data are needed to help with interpretation of data from irradiated materials, to develop and validate phase diagrams and models of U-Zr and more complex systems, to inform and validate fuel performance codes, to design fuels for future fast reactors, and to guide future experimental investigations to fill in crucial gaps in knowledge.
This paper provides a summary and critical review of the available experimental data on phases and phase diagrams, electrical properties, thermal expansion, thermal conductivity, heat capacity, mechanical properties, vapor pressures, and thermodynamic properties of unirradiated U-10Zr alloys. Many of the reported values were published before approximately 1970 and are available only in obscure reports. This critical review concludes by identifying areas where additional experimental measurements are particularly necessary and makes recommendations on prioritization of new measurements with a view to the emerging needs associated with the mechanistic modeling of nuclear fuels and their performance.