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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
V.L. Arbuzov, V. B. Vykhodets, G. A. Raspopova
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1127-1131
Tritium Properties and Interaction with Material | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30558
Articles are hosted by Taylor and Francis Online.
The interaction of radiation-induced defects with deuterium atoms at room tenperature was studied for commercial vanadium, V-H and V-D alloys. During a 700 keV D+ bombardment the accumulation of D in the irradiated area was measured by means of NRA using the reaction D(d,p)T. It was shown that in the irradiated area of the V-D alloys (0.01–0.1 at .% D) the D concentration depends on both the fluence and the alloy composition. As the fluence is increased, the accumulated amount saturates. The saturation level depends on the D concentration and is 3 to 6 times as high as the D concentration in the bulk. The D segregation is due to the formation of immobile or low-mobile “D atom — radiation defect” conplexes. At the same time free D atoms are almost immediately redistributed in the bulk of the sample. A complex deuterium-protium segregation in V-D and V-H alloys under D+ bombardment was studied too. The accumulation of implanted deuterium in the irradiation-damaged area was examined for alloys with a high (0.6–2.65 at .% H) content of 1H hydrogen isotope. It is shown that the implant accumulation level is indepedent of the bombardment dose but is determined by the content of “free” protium in the alloys: the higher the protium concentration, the lower the accumulation level.