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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.
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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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ORAU, ANS, others to host workshops on nuclear academic programs
Oak Ridge Associated Universities (ORAU), in partnership with the American Nuclear Society, the Nuclear Energy Institute, and the Institute for Nuclear Power Operators, has announced it will host an online workshop called “Shaping the Future of Nuclear Academic Programs.” The 90-minute program is designed for university department heads and faculty interested in enhancing nuclear science and technology programs through best practices.
K. Samec
Nuclear Technology | Volume 162 | Number 3 | June 2008 | Pages 358-378
Technical Paper | Accelerators | doi.org/10.13182/NT08-A3962
Articles are hosted by Taylor and Francis Online.
A significant milestone in the Megapie project, the world's first liquid-metal neutron spallation source, was reached when its containment structure was proof tested in a full-scale liquid-metal leak experiment. The experimental apparatus used in testing the effects of a liquid-metal leak of lead-bismuth eutectic on a heavy-water-cooled confinement at full scale is described. Measurements taken during the experiment validated the design chosen for the containment, a water-cooled aluminium double hull, and demonstrated that the experimental apparatus was capable of reproducing an accidental leak. The data acquired during this one-off experiment can be used in the future to assess liquid-metal leaks analytically.In the event of a catastrophic failure in the spallation source, the experiment proved that the products of the ensuing liquid-metal leak would be safely contained and cooled. Furthermore, analytical methods used in predicting the outcome of a leak were validated. Indeed, transient fluid-dynamics, thermal and thermostructural calculations performed ahead of the test to predict temperatures and stresses in the aluminum containment and temperatures of the cooling loop agreed well with measurements.