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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
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.
Tetsuji Noda, Hiroshi Araki, Hiroshi Suzuki
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 962-966
Material Interaction and Permeation | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22728
Articles are hosted by Taylor and Francis Online.
The desorption behavior of deuterium from molybdenum, Mo-0.001 mass %C, Mo-0.06-0.092 mass %B, tungsten and W-0.011 mass %C prepared with arc-melting in Ar-10%D2 was studied using a vacuum desorption method in the temperature range of 533–1152K. The diffusivity of deuterium measured for molybdenum was D=4.97x10−7 exp(−36.7kJ/mol/RT)m2s−1 and D=1.77x10−6 exp(−55.8kJ/mol/RT)m2s−1 for tungsten. The diffusivity of deuterium for both molybdenum and tungsten decreased with an addition of C and B. This decrease was considered due to the trap effect of carbide and boride. The trapping energy estimated was 54 kJ/mol for Mo-C and Mo-B and 82kJ/mol for W-C.