Lightbridge Corporation’s Advanced Metallic Fuel for Light Water Reactors

Malone, James P.; Totemeier, Aaron; Shapiro, N.L.; Vaidyanathan, S.

doi:10.13182/nt12-a15354

Cited by 53 publications

(4 citation statements)

References 7 publications

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“…To enhance the economic benefit of nuclear energy, it is imperative to achieve power updates or extend the refueling cycle in Pressurized Water Reactors [1]. An advanced U-Zr metal-based helical cruciform fuel (HCF) has been developed recently by Lightbridge [2][3][4]. In the HCF rod, the U-Zr metallic fuel core is metallurgically bonded with the zirconium alloy cladding.…”

Section: Introductionmentioning

confidence: 99%

Modeling of Zirconium Atom Redistribution and Phase Transformation Coupling Behaviors in U-10Zr-Based Helical Cruciform Fuel Rods under Irradiation

Chen,

Xie,

Mao

et al. 2024

Metals

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Uranium–zirconium metal-based Helical Cruciform Fuels (HCFs) have shown a promising prospect for their use in advanced nuclear reactors. However, during irradiation, dual-phase coexistence and the spatial heterogeneous distribution of zirconium atoms occur at higher powers, affecting the thermo-mechanical coupling behaviors and safety of fuel elements and assemblies. In this study, based on the phase-field approach, the coupled multi-field governing equations to describe the zirconium diffusion and phase evolution for U-Zr metallic fuels are improved. Furthermore, the corresponding numerical algorithms and procedures for multi-field coupling calculations are developed. The numerical predictions of zirconium atom fraction are in good agreement with the relevant experimental results, validating the developed models, algorithms and programs. The zirconium atom redistribution and phase transformation coupling behaviors in high-power U-10wt%Zr-based HCF rods are also obtained. Moreover, the complex evolution mechanisms of multi-field variables are analyzed. The results indicate the following: (1) the irradiation enhancement of the thermal mobility and chemical mobility plays a critical role in the redistribution of Zr atoms; (2) the multi-field results of HCF rods have helical symmetric characteristics; (3) the contribution competitions of the temperature gradient and chemical potential gradient within the α phase and γ phase significantly influence the zirconium-atom redistribution, with the zirconium-rich zones formed in the elbow region and the zirconium-poor zones appearing inside. These research efforts supply a foundation for the further involvement of mechanical fields in multi-field coupling computation.

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Section: Introductionmentioning

confidence: 99%

Modeling of Zirconium Atom Redistribution and Phase Transformation Coupling Behaviors in U-10Zr-Based Helical Cruciform Fuel Rods under Irradiation

Chen,

Xie,

Mao

et al. 2024

Metals

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“…[ 1 ] [ 2 ] Lightbridge's multilobed helical fuel geometry uses its characteristic twist to enhance turbulent mixing and increase safety margins. [ 3 ] With recent advancements in additive manufacturing technology, research on complex geometries that were previously impractical to fabricate have gained popularity. Triply Periodic Minimal Surface (TPMS) is a particularly popular choice.…”

Section: Introductionmentioning

confidence: 99%

Triply Periodic Minimal Surfaces Lattice Neutronics Scoping Studies

Fritsch,

Martin

2023

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Triply periodic minimal surfaces (TPMSs) have seen extensive research in heat exchanger development due to their enhanced heat transfer performance. When applied to reactor cores, TPMSs can more efficiently dissipate heat to the coolant, permitting increased power densities. The increased power density can be used to develop smaller reactors while retaining power output. Although TPMS core geometries promise enhanced heat transfer, the neutronic behavior of such geometries requires further inquiry. In this study, the neutron multiplication and buckling are compared between variations of the TPMS and traditional pincell core designs.

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“…IGHTBRIDGE Corporation is a U.S. company that has developed a design and fabrication process for a novel nuclear fuel [1], consisting of helically twisted metallic Uranium-Zirconium alloy fuel rods. Lightbridge's fuel technology can improve plant safety, significantly enhance the nuclear power industry's economics and increase power output of existing and new light water nuclear reactors.…”

Section: Introductionmentioning

confidence: 99%

Measurement station for interim inspections of Lightbridge metallic fuel rods at the Halden Boiling Water Reactor

Hartmann

Totemeier²,

Holcombe

et al. 2018

EPJ Web Conf.

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Lightbridge Corporation has developed a new Uranium-Zirconium based metallic fuel. The fuel rods aremanufactured via a co-extrusion process, and are characterized by their multi-lobed (cruciform-shaped) cross section. The fuel rods are also helically-twisted in the axial direction. Two experimental fuel assemblies, each containing four Lightbridge fuel rods, are scheduled to be irradiated in the Halden Boiling Water Reactor (HBWR) starting in 2018. In addition to on-line monitoring of fuel rod elongation and critical assembly conditions (e.g. power, flow rates, coolant temperatures, etc.) during the irradiation, several key parameters of the fuel will be measured out-of-core during interim inspections. An inspection measurement station for use in the irradiated fuel handling compartment at the HBWR has therefore been developed for this purpose. The multi-lobed cladding cross section combined with the spiral shape of the Lightbridge metallic fuel rods requires a high-precision guiding system to ensure good position repeatability combined with low-friction guiding. The measurement station is equipped with a combination of instruments and equipment supplied from third-party vendors and instruments and equipment developed at Institute for Energy Technology (IFE). Two sets of floating linear voltage differential transformer (LVDT) pairs are used to measure swelling and diameter changes between the lobes and the valleys over the length of the fuel rods. Eddy current probes are used to measure the thickness of oxide layers in the valleys and on the lobe tips and also to detect possible surface cracks/pores. The measurement station also accommodates gamma scans. Additionally, an eddy-current probe has been developed at IFE specifically to detect potential gaps or discontinuities in the bonding layer between the metallic fuel and the Zirconium alloy cladding. Potential gaps in the bonding layer will be hidden behind a 0.5-1.0 mm thick cladding wall. It has therefore been necessary to perform a careful design study of the probe geometry. For this, finite element analysis (FEA) has been performed in combination with practical validation tests on representative fuel dummies with machined flaws to find the probe geometry that best detects a hidden flaw. Tests performed thus far show that gaps down to 25 μm thickness can be detected with good repeatability and good discrimination from lift-off signals.

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Lightbridge Corporation’s Advanced Metallic Fuel for Light Water Reactors

Cited by 53 publications

References 7 publications

Modeling of Zirconium Atom Redistribution and Phase Transformation Coupling Behaviors in U-10Zr-Based Helical Cruciform Fuel Rods under Irradiation

Modeling of Zirconium Atom Redistribution and Phase Transformation Coupling Behaviors in U-10Zr-Based Helical Cruciform Fuel Rods under Irradiation

Triply Periodic Minimal Surfaces Lattice Neutronics Scoping Studies

Measurement station for interim inspections of Lightbridge metallic fuel rods at the Halden Boiling Water Reactor

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