Synthesis and sintering of UN-UO2 fuel composites

Jaques, Brian J.; Watkins, Jennifer K.; Croteau, Joseph R.; Alanko, Gordon A.; Tyburska-Püschel, B.; Meyer, M. K.; Xu, Peng; Lahoda, E.J.; Butt, Darryl P.

doi:10.1016/j.jnucmat.2015.06.029

Cited by 53 publications

(14 citation statements)

References 31 publications

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“…UN powders were synthesized from depleted α-uranium (99.4% purity, 50 mesh) using a hydride-dehydride-nitride thermal synthesis route [41]. Compacts of UN-5UO2 were fabricated using the synthesized UN powders and UO2 (99.8% purity, 50 mesh) from Bio-Analytical Industries Incorporated (Boca Raton, FL).…”

Section: Methodsmentioning

confidence: 99%

“…The pellets were sintered for 5 hours at 1900 °C in an Ar + 100 ppm N2 atmosphere. Details of the sintering process are provided in a previous publication [41]. After sintering, the pellets were immediately transferred to an inert atmosphere glovebox.…”

Section: Methodsmentioning

confidence: 99%

“…However, UN has unproven performance in accident scenarios, such as a fuel cladding breach where the fuel pellet would be exposed to water coolant or steam [34][35][36][37][38][39]. It has been proposed that the addition of secondary phases, such as UO2 and U3Si2, can mitigate the chemical reaction of UN with water or steam [40][41][42][43].…”

Section: Introductionmentioning

confidence: 99%

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Phase and defect evolution in uranium-nitrogen-oxygen system under irradiation

Khafizov

Jiang

et al. 2021

Acta Materialia

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Section: Methodsmentioning

confidence: 99%

Section: Methodsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Phase and defect evolution in uranium-nitrogen-oxygen system under irradiation

Khafizov

Jiang

et al. 2021

Acta Materialia

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“…A variety of studies using d-UO2 as a UO2 surrogate exist spanning a wide range of topics, only a few of which are referenced here for brevity. These include synthesis of thin UO2 films from electron beam evaporation of UO2 pellets, mechanical properties of nuclear fuel surrogates using picosecond laser ultrasonics, characterization of minor actinide MOX fuel, microstructural evolution of simulated high burn-up structures, synthesis and sintering of nitride-oxide composites, and Raman spectroscopy for corrosion product identification on UO2 [15,[50][51][52][53][54].…”

Section: Depleted Uranium Oxide (D-uo2) As a Surrogate For Uo2mentioning

confidence: 99%

Report on technical activities and technical plan for university advanced manufacturing work for in-pile sensors

McMurtrey

Ilevbare

Rooyen

2017

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The In-Pile Initiative is working to develop and deploy novel instrumentation that may be used to characterize and monitor the behavior of fuels and materials within a nuclear reactor core during operation. The extreme conditions (temperature, environment, irradiation, etc.) make measurements difficult, which has resulted in typical characterizations being performed post-irradiation. This initiative has been divided into a number of work packages, with the focus of this work package being the development of advanced manufacturing techniques to support to novel sensor designs of the other work packages. This work is being performed at Idaho National Laboratory in collaboration with groups at both the University of Notre Dame and Boise State University. This report details the technical plans for the university work to address the goals of this work package. To accelerate sensor research and development for in-pile measurements, the University of Notre Dame will focus on the development of an advanced additive manufacturing method, direct ink writing (DIW), to fabricate sensors of various designs and functions (including sensors with multiple functions). Their work is divided into two main objectives: 1) The development of direct-ink writing additive manufacturing equipment, process monitoring and control, and 2) the development of new materials processing and characterization methodologies for additive manufacturing. In the second objective, the work at the University of Notre Dame will be supporting the work of Boise State University as they develop new inks for printing sensors. The work being performed at Boise State University is divided into four objectives: 1) Nuclear grade nanoparticle ink synthesis, 2) advanced manufacturing process control through computer simulation, 3) prototypical surrogate sample development (to simulate fuel) for advanced manufacturing and 4) advanced manufacturing process qualification for the direct write inks. The modelling and simulation work in objective 2 will support the process sensing and control work being performed at the University of Notre Dame.

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“…Uranium dioxide remains the leading nuclear fuel material globally owing to its relative ease of manufacture, stability under normal and off-normal operating conditions, extremely high melting point and benign reactions with the various nuclear reactor coolants currently in useespecially within water-based reactors. Looking forward, UO2-based fuels are being considered in a number of advanced technology fuel conceptsfrom increased enrichment (>5 wt.% 235 U) of standard UO2 pellets, doped UO2 pellets (common dopants include Cr2O3 [1], alumino-silicates [2] and TiO2 [2] [3]) and the more advanced UO2-composite fuels, whereby UO2 is combined with phases that have higher thermal conductivity and/or higher uranium density to improve fuel cycle costs and in reactor performance, for example: uranium mononitride [4] and beryllium oxide [5].…”

Section: Introductionmentioning

confidence: 99%