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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
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.
Aaron Aoyama, James Blanchard, John Sethian, Nasr Ghoniem, Shahram Sharafat
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 435-440
IFE Drivers and Chambers | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8940
Articles are hosted by Taylor and Francis Online.
In support of the High Average Power Laser (HAPL) project the Electra Laser, a KrF Gas Laser system is being developed at NRL. The laser uses high voltage (500 - 800 keV), high current (100 - 500 kA), short pulse (100 - 600 ns) electron beams to pump the 0.14 MPa (20 psi) pressurized KrF gas cell, which is separated from the vacuum region by a 25 m-thick stainless steel foil, the Hibachi Foil. The foil is made of SUS304, operates between 180 °C and 450 °C, and has typical dimensions of about 0.3 m × 1.0 m. The laser pulses at up to 5 Hz, and the foil is subjected to repetitive thermal and mechanical stresses. In typical experiments, the foil lasts 1000 - 20,000 shots before suffering a catastrophic failure. In an attempt to improve foil performance a variety of design modifications are being considered along with changes in foil material. Earlier Hibachi foil designs used flat foils resting on 0.3 m long square water-cooled supporting ribs (1 cm wide). There is a 3.4 cm gap between ribs. . Advanced Hibachi foil concepts are under development using a scalloped foil design. In this paper we report on the comparative thermo-mechanical analysis between flat and scalloped foil geometries. It is demonstrated that the scalloped design reduces stresses to within yield limits of the stainless steel material.