U-Mo Based Fuel System

Leenaers, A.; Wight, Jared; Berghe, S. Van den; Ryu, Ho Jin; Valery, J.F.

doi:10.1016/b978-0-12-803581-8.11775-8

Cited by 5 publications

(7 citation statements)

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“…When used in the typical aluminium matrix dispersion fuel, with a fabrication-based limit of about 50 volume percent, the achievable fuel meat loading is ∼8 gU/cc in the fuel meat. The UMo dispersion fuel behavior has been studied in the irradiation experiments such as FUTURE, IRIS, E-FUTURE, and SELENIUM, [8][9][10][11][12], and most recently in the LEU-FOREvER project irradiation named: SEM-PER FIDELIS [13,14] (all irradiated in BR2). The current state-of-the-art development is targeting the reduction of the detrimental swelling of UMo-Al fuel plates at high power and high burnup by heat treatment, ZrN PVD coating of the UMo particles [15], and adding a small amount of silicon in the matrix.…”

Section: Umo Dispersion Fuelmentioning

confidence: 99%

“…Most of this project has been executed, and it is expected to be fully completed in late 2022. The fuel performance understanding and the fabrication equipment and processes of the UMo dispersion fuel system [8,10] have significantly matured during the project. The increased fuel performance understanding was primarily based on the FDEG review of the SEMPER-FIDELIS [28] experiment that was irradiated in ATR and examined in the previous Euratom project: HERACLES-CP [29].…”

Section: Project-specific Innovations 41 Leu-forever Projectmentioning

confidence: 99%

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Innovation and qualification of LEU research reactor fuels and materials

Wight

Valance

Holmström

2023

EPJ Nuclear Sci. Technol.

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Two projects within the Euratom Research and Training Programmes 2014–2018 and 2019–2020 are focused on the innovation and qualification of novel nuclear fuels for conversion from highly-enriched uranium to low-enriched uranium (LEU) and for securing the supply chain of EU research reactors into the future. The LEU-FOREvER project is drawing to a close and has made significant progress in developing and demonstrating the uranium-molybdenum fuel system, demonstrating the viability of a high-density uranium-silicide fuel for EU high-performance research reactors (BR2, RHF, FRM-II, JHR). This project has significantly increased the fabrication know-how and fuel performance understanding of the uranium-molybdenum and high-density uranium-silicide dispersion fuel systems. Further, a new, innovative and increased performance design for the LVR-15 research reactor fuel assembly has been engineered and a demonstration is planned in 2022. In the EU-QUALIFY project, which began in 2020, the planning of four demonstration irradiation tests has been nearly completed and fabrication development of the various fuel systems is ongoing, including the establishment of an EU monolithic uranium-molybdenum fabrication capability. It is expected that the results of this project will begin or complete the data gathering necessary for generic fuel qualification of the LEU uranium-molybdenum dispersion and monolithic fuel systems, and the LEU high-density uranium-silicide fuel system.

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Section: Umo Dispersion Fuelmentioning

confidence: 99%

Section: Project-specific Innovations 41 Leu-forever Projectmentioning

confidence: 99%

Innovation and qualification of LEU research reactor fuels and materials

Wight

Valance

Holmström

2023

EPJ Nuclear Sci. Technol.

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“…Among them, transition metal-stabilised hightemperature cubic γ-allotropes of uranium are highly promising. For instance, the addition of approximately 7 -10 wt% of molybdenum to uranium has been intensively studied as a fuel for RTRs due to the high chemical stability of the γ-U(Mo) phase, its stability under irradiation and the increased density of uranium (ρ U ≈ 16-17 g U cm −3 ) (Snelgrove et al 1997, Leenaers et al 2020a. Other materials under consideration include U 3 Si 2 (ρ U ≈ 11.3 g U cm −3 ) (Leenaers et al 2020b), UN (ρ U ≈ 13.5 g U cm −3 ) (Durand andLaudamy 1994, Wallenius 2020), UC (ρ U ≈ 13.0 g U cm −3 ) (Clement Ravi Chandar et al 2020) and UB 2 (ρ U ≈ 11.7 g U cm −3 ) (Turner et al 2020) among others.…”

Section: Introductionmentioning

confidence: 99%

From caged compounds with isolated U atoms to frustrated magnets with 2- or 3-atom clusters: a review of Al-rich uranium aluminides with transition metals

Pasturel,

Pikul

2024

Rep. Prog. Phys.

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Crystal structures and physical properties of four families of Al-rich ternary uranium compounds with transition metals (TE) are reviewed, namely UTE2Al20, UTE2Al10, U6TE4Al43, and U3TE4Al12. The compounds can be described as consisting of 1 (isolated), 2 (dumbbells) or 3 (triangles) uranium atom clusters, surrounded (1-2-20, 1-2-10 and 6-4-43) or not (3-4-12) by large cages, whichstrongly influence their magnetic and related properties. Indeed, the ground states of the described systems evolve from Curie-like paramagnetism in the case of the phases with well-isolated, single U-atoms, to complex magnetic order or possible frustrated magnetism in the case of the systems with uranium triangles forming a breathing kagome lattice. We argue that the four families of uranium aluminides described in this review provide a unique opportunity to study magnetic interactions between U magnetic moments while gradually increasing the number of their nearest magnetic neighbors, and may also be helpful in understanding the fundamental origin of magnetic freezing phenomena.

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“…It is known that the fuels dominated by α−U easily trigger high fission gas swelling [9]. In addition, the concentration of the Mo element affects the thermo-mechanical properties of U-Mo alloys, including the elastic parameters [14][15][16], the thermal conductivity [15,16], the tensile strength [14,15] and the creep behaviors [15,17]. At lower Mo concentrations, the Young's modulus and tensile strength of un-irradiated U-Mo alloys are reduced [14], and the thermal conductivity and creep rate increase [15][16][17].…”

Section: Introductionmentioning

confidence: 99%

“…In addition, the concentration of the Mo element affects the thermo-mechanical properties of U-Mo alloys, including the elastic parameters [14][15][16], the thermal conductivity [15,16], the tensile strength [14,15] and the creep behaviors [15,17]. At lower Mo concentrations, the Young's modulus and tensile strength of un-irradiated U-Mo alloys are reduced [14], and the thermal conductivity and creep rate increase [15][16][17]. Consequently, the local depletion of Mo is responsible for occurrences of cracking and enlarged porosity near the U-Mo/Zr interface of the irradiated U-10Mo monolithic fuel plate [10].…”

Section: Introductionmentioning

confidence: 99%

Prediction and Deformation Mechanism Analysis of High Porosity in U–10Mo Monolithic Fuels at High Burnup

Jian,

Zhao,

Ding

2023

Metals

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High porosity phenomena of U-10Mo fuel foil appear in the U–Mo/Al monolithic fuel plate under deep burnup. In this study, the fuel skeleton creep-based bubble growth model is further improved with the intrusion effect of solid fission products, multiplying the reduction factor in the bubble volume to obtain the bubble pressure. With the locally enhanced irradiation creep of the Mo-depleted region considered, a simulation of the thermo-mechanical coupling behaviors of the monolithic fuel plate L1P7A0 is carried out, based on the commercial finite element (FE) analysis code ABAQUS. A fission-induced creep rate coefficient of 250 × 10−22 mm3/(fission·MPa) is identified for the Mo-depleted region, with the predictions of porosity and the thickness deformation of U–Mo fuel foil agreeing well with the experimental data. The research results indicate that: (1) the locally enhanced fuel skeleton creep ability is responsible for the higher porosities near the U–Mo/Zr interface; (2) the entrance of solid fission products into the fission bubbles at high burnup is the dominant factor in inducing high porosity in the regions of the most heavily irradiated fuel foil, especially near the fuel foil edge bearing the elevated external hydrostatic pressures; (3) with the intrusion effect of solid fission products considered, the prediction of the porosity increases from ~15% to ~35% near the fuel foil edge; (4) the intrusion of solid fission products leads to extra differences between the bubble pressure and the external pressure, and simultaneously results in the strengthened fuel skeleton creep deformation contributions to the bubble growth.

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U-Mo Based Fuel System

Cited by 5 publications

References 59 publications

Innovation and qualification of LEU research reactor fuels and materials

Innovation and qualification of LEU research reactor fuels and materials

From caged compounds with isolated U atoms to frustrated magnets with 2- or 3-atom clusters: a review of Al-rich uranium aluminides with transition metals

Prediction and Deformation Mechanism Analysis of High Porosity in U–10Mo Monolithic Fuels at High Burnup

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