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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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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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
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How to talk about nuclear
In your career as a professional in the nuclear community, chances are you will, at some point, be asked (or volunteer) to talk to at least one layperson about the technology you know and love. You might even be asked to present to a whole group of nonnuclear folks, perhaps as a pitch to some company tangential to your company’s business. So, without further ado, let me give you some pointers on the best way to approach this important and surprisingly complicated task.
Yasuhisa Oya, Misaki Sato, Hiromichi Uchimura, Naoko Ashikawa, Akio Sagara, Naoaki Yoshida, Yuji Hatano, Kenji Okuno
Fusion Science and Technology | Volume 67 | Number 3 | April 2015 | Pages 515-518
Proceedings of TRITIUM 2013 | doi.org/10.13182/FST14-T68
Articles are hosted by Taylor and Francis Online.
The effect of carbon implantation for the dynamic recycling of deuterium, which demonstrates tritium recycling, including retention and sputtering, was investigated using in-situ sputtered particle measurements. The C+ implanted W, WC and HOPG were prepared and dynamic sputtered particles were measured during H2 + irradiation. It was found that the major hydrocarbon species for C+ implanted tungsten was found to be CH3, although those for WC and HOPG were CH4. The chemical state of hydrocarbon is controlled by the H concentration in a W-C mixed layer. The amount of C-H bond and the retention of H trapped by carbon atom should control the chemical form of hydrocarbon sputtered by H2+ irradiation and the desorption of CH3 and CH2 was due to chemical sputtering, although that for CH was physical sputtering. The activation energy for CH3 desorption was estimated to be 0.4 eV, corresponding to the trapping process of hydrogen by carbon through the diffusion in W. It was concluded that the chemical states of hydrocarbon sputtered by H2+ irradiation for W was determined by the amount of C-H bond on the W surface.