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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
Standards Program
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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February 2024
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.
Vincent Hedberg, Mikhail Morev, Marco Silari, Zuzana Zajacová
Nuclear Technology | Volume 173 | Number 3 | March 2011 | Pages 327-331
Technical Note | Radiation Measurements and Instrumentation | doi.org/10.13182/NT11-A11666
Articles are hosted by Taylor and Francis Online.
Predictions of high-energy hadron activation of liquid argon in the calorimeter of A Thoroidal LHC ApparatuS (ATLAS) were carried out by folding particle flux spectra with the radionuclide production cross sections. Calculations were performed with a wide array of input data. Six sets of cross sections were folded with two sets of particle flux spectra, and the results were compared. The particle fluxes were obtained from simulations with the Monte Carlo radiation transport codes FLUKA and GCALOR. The cross-section sets were calculated according to the Rudstam and the Silberberg-Tsao formulas; taken from the Japanese Evaluated Nuclear Data Library (JENDL) and the Medium Energy Nuclear Data Library (MENDL); obtained from the Large Hadron Collider air activation studies; and compiled from various, predominantly experimental, sources.