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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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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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.
T. Hayashi, T. Suzuki, M. Yamada, M. Nishi
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 510-514
Fueling and Tritium Handling Technology (Poster Session) | doi.org/10.13182/FST98-A11963663
Articles are hosted by Taylor and Francis Online.
The accountancy of tritium stored in the Zirconium-Cobalt (ZrCo) bed with 25 g of tritium storage capacity has been investigated by “in-bed” gas flowing calorimetric method for a few years. This type of calorimetry uses the temperature raise of helium (He) gas circulated through a secondary coil line installed in the ZrCo tritide. Recently, the basic calorimetric characteristics was demonstrated well within 1 % accuracy of the ITER requirement using 22 g of tritium under actual storage system conditions, such as hydrogenation-dehydrogenation of tritium, long-term storage (3He accumulation inside of tritide vessel), and DT mixture storage. Based on the experimental data, a 100 g of tritium storage bed (ITER size) was designed and its calorimetric performance was discussed.
