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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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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.
C. Jong, J. Knaster, C. Sborchia
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 666-671
ITER | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST09-A8985
Articles are hosted by Taylor and Francis Online.
The Toroidal Field (TF) system of ITER consists of 18 coils in which the winding pack (WP) is formed by 7 stacked double pancakes (DP). The conductors in the TF coil are operated in steady state mode with a current of 68 kA providing a flux of 5.4 T at the plasma axis. The conductors are wrapped with turn insulation and embedded in grooves manufactured in so called radial plates. The grooves are closed with covers, wrapped with glass and polyimide tapes and vacuum impregnated. This layout of the TF WP prevents the accumulation of stresses in the turn insulation, making unlikely the occurrence of a turn-to-turn short circuit. The insulation of the WP will undergo during ITER design lifetime fast neutron fluencies up to 3.2x1021n/m2, which is equivalent to 10 MGy. Standard epoxies degrade if submitted to such doses, developing mechanical properties that would not withstand the estimated operation in-plane shear stress in the range of 45 MPa. The use of a radiation-hard thermoset for glass-fiber composites (cyanate ester) is considered and the on-going extensive qualification work will be presented. The technical solution of how to isolate critical High Voltage (HV) areas like the joint connections or voltage taps is also discussed.