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Lightbridge announces first U-Zr fuel rod samples extruded at INL
Lightbridge Corporation announced today that it has reached “a critical milestone” in the development of its extruded solid fuel technology. Coupon samples using an alloy of zirconium and depleted uranium—not the high-assay low-enriched uranium (HALEU) that Lightbridge plans to use to manufacture its fuel for the commercial market—were extruded at Idaho National Laboratory’s Materials and Fuels Complex.
Daniel Papp, Dinh Truong, Alice Ying, Nicola Zaccari
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 1058-1063
Fusion Materials | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST09-A9051
Articles are hosted by Taylor and Francis Online.
Lithium metatitanate (Li2TiO3) is a candidate tritium breeding material for fusion reactor blankets. In an actual blanket the pebbles are geometrically confined in a containing structure subjected to displacement and stress constraints under operating conditions. For an accurate description of pebble behavior during operations, existing data of pebble deformation under compressive loads is inadequate. In this study a uniaxial compression experimental apparatus was built to investigate time dependent creep on a single pebble as a function of applied force and temperature relevant to blanket conditions. Experimental results shows that at a temperature range of 700-800 °C, the crush load of Li2TiO3 pebbles is reduced by about half of its room temperature crush load. The experimental results allow for the establishment of a pebble creep failure map as a function of force and temperature, which provides guidance to the blanket designs. The study also introduces an FEA model based on experimental deformation data to obtain the constitutive equation needed for Discrete Element Model simulation of the pebble bed.