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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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Nuclear Science and Engineering
February 2025
Nuclear Technology
Fusion Science and Technology
Latest News
A more open future for nuclear research
A growing number of institutional, national, and funder mandates are requiring researchers to make their published work immediately publicly accessible, through either open repositories or open access (OA) publications. In addition, both private and public funders are developing policies, such as those from the Office of Science and Technology Policy and the European Commission, that ask researchers to make publicly available at the time of publication as much of their underlying data and other materials as possible. These, combined with movement in the scientific community toward embracing open science principles (seen, for example, in the dramatic rise of preprint servers like arXiv), demonstrate a need for a different kind of publishing outlet.
Yuji Torikai, A. N. Perevezentsev, Masao Matsuyama, Kuniaki Watanabe
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 736-740
Decontamination and Waste | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-2
Articles are hosted by Taylor and Francis Online.
To establish efficient decontamination methods for tritium-contaminated stainless steels, the desorption of tritium was studied for SS-316 in dry and wet argon gas carriers at different temperatures. The specimen was exposed to tritium at 523 K for 3 hours. The tritium inventory was in a range from 2 to 12 MBq. The desorption at elevated temperatures was measured by using a liquid scintillation counter. In addition, the tritium depth profiles in the specimen were evaluated by β-ray induced X-ray spectrometry. It was found that the decontamination efficiency was enhanced by the presence of moisture. This effect was ascribed to the isotope exchange reaction on the surface. The depth profile measurements revealed the presence of tritium-rich subsurface layer and the bulk with lower tritium concentration. The majority of tritium was, however, found in the bulk, indicating that extraction of bulk tritium is essential for the decontamination of SS-316 exposed to tritium at high temperatures.
