Temperature Effect of Gas Bubble Evolution in UCN Fuel Kernels Irradiated by Swift Xe Ions

Bhattacharya, Sumit; Miao, Yinbin; Mo, Kun; Jamison, Laura; Seibert, Rachel; Nelson, Andrew T.; Connaway, Heather M.; Yacout, Abdellatif M.

doi:10.2172/1807666

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Programmatic and Industry Considerations Of Un/mox1

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2023

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“…DOE Advanced Reactor Demonstration Program (ARDP) risk reduction funding was awarded to BWXT [68] to pursue a gas microreactor design that utilize TRISO fuel with UN kernels, which will be tested at INL using a new irradiation test train developed at NRIC [69]. In addition, the DOE NEAMS program is also pursuing modeling and simulation activities related to UN [70,71], and finally NNSA is also investigating UN fuel [72].…”

Section: Programmatic and Industry Considerations Of Un/moxmentioning

confidence: 99%

Survey of Uranium Nitride and Mixed Oxide Fuels for Microreactor Applications

Yacout,

Miao

2023

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The DOE-NE is supporting the development and deployment of microreactors through the activities of the microreactor program. As part of its activities, the program is surveying available fuel types and data in support of their use in microreactor systems. This survey of fuel candidates for microreactors aims at identifying gaps that need further research through programs such as the Advanced Fuels Campaign (AFC). ANL scope is focused on the potential of using uranium nitride (UN) and mixed oxide (MOX) fuels in microreactors. This report provides a summary survey of available information related to those fuel systems, including properties, irradiation and performance data, as well as fabrication, and identifies data and technology gaps related to those fuel systems that needs to be addressed so they can be considered for use in microreactors.vi

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Section: Programmatic and Industry Considerations Of Un/moxmentioning

confidence: 99%