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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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Fusion Science and Technology
Latest News
Argonne to investigate Pu chemistry to aid Hanford cleanup
Researchers at the Department of Energy’s Argonne National Laboratory are investigating the details of plutonium chemistry with the goal of aiding the cleanup of the Hanford Site in Washington state. For more than 40 years, reactors located at Hanford produced plutonium for America’s defense program, resulting in millions of gallons of liquid radioactive and chemical waste.
D. L. Hillis, J. T. Hogan, P. Andrew, J. Ehrenberg, M. Groth, M. von Hellermann, L.D. Horton, R. Monk, P. Morgan, M. Stamp
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 941-945
Plasma Facing Components Technology (Poster Session) | doi.org/10.13182/FST98-A11963734
Articles are hosted by Taylor and Francis Online.
Future fusion reactors, like ITER, will rely on an active exhaust system to pump tritium (T) in the divertor and then recirculate it to the fuel stream. Estimation of the T inventory requires a detailed T balance, which determines if T is preferentially enriched relative to D in its pathway from the main plasma to the divertor and pump. On the Joint European Torus (JET), the neutral T concentration in the sub-divertor (pumping plenum and region below the divertor strike point plate) is measured with a modified Penning gauge coupled to a high-resolution spectrometer. In addition, T concentration measurements are made in the plasma edge and strike point region with a spectrometer viewing these regions. The sub-divertor and divertor (region above the strike point plate) T concentration measurements show differences during initial T uptake and retention which are characteristic of wall deposition properties. Since wall retention is one of the factors in calculating the eventual T inventory in a reactor, a detailed study of this process has been undertaken.