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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Fusion Science and Technology
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
A. Klix, Ch. Adelhelm, U. Fischer, D. Gehre, T. Kaiser
Fusion Science and Technology | Volume 62 | Number 1 | July-August 2012 | Pages 196-203
Blanket Materials Technology | Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology | doi.org/10.13182/FST12-A14135
Articles are hosted by Taylor and Francis Online.
A consortium of several European laboratories has performed neutronics experiments with a representative mock-up of the European helium-cooled lithium-lead (HCLL) test blanket module (TBM) irradiated with DT neutrons from intense neutron generators. The aim of these experiments was to provide experimental data for checking nuclear data and calculational tools for the prediction accuracy of important parameters such as the tritium production rate and neutron and gamma-ray flux spectra. The mock-up consisted of bricks of solid LiPb arranged in layers separated by Eurofer sheets. The 6Li concentration in the LiPb determines the slow neutron flux distribution in the mock-up, and an accurate knowledge of this value is of paramount importance for the analysis of these neutronics experiments. The analysis of the tritium production rate experiments revealed discrepancies between the real 6Li concentration and the one specified by the manufacturer of the LiPb (natural Li composition). Here we report on the investigation of the 6Li concentration in the LiPb with several experimental techniques: 1) time-of-arrival neutron spectra measured inside the mock-up irradiated with short pulses of 14-MeV neutrons from a DT neutron generator, 2) transmission measurements on LiPb bricks with moderated neutrons from an AmBe source to check for differences between bricks, and 3) mass spectroscopic methods on small samples taken from selected LiPb bricks. We found that the 6Li concentration varies only very little between the bricks. The weight fraction of lithium in the LiPb was 0.61 wt% as quoted by the manufacturer, but the 6Li abundance was half of the natural value in lithium, 3.8 at% instead of 7.5 at%.