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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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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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.
Kenzo Munakata, Akinori Koga, Yoshihiro Yokoyama, Seigo Kanjo, Satoshi Yamatsuki, Dmitri Ianovski, Masabumi Nishikawa
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 1064-1068
Blanket Material and Process | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22747
Articles are hosted by Taylor and Francis Online.
In most current designs of D-T fusion reactor blankets employing ceramic breeder materials, the use of a helium sweep gas containing 0.1 % of hydrogen is contemplated to extract tritium efficiently via isotopic exchange reactions. However, the isotope exchange reaction proceeds fast only at the more elevated temperatures, so that the rate of isotope exchange reactions is considerably low at lower temperatures. Taking into consideration that there is a broad temperature distribution within a blanket module, it is anticipated that the tritium bred in regions of lower temperatures will be poorly recovered. For this reason, there is still a need to develop techniques that contribute to the acceleration of the recovery of bred tritium at lower temperatures. In our previous works, the effect of catalytic active metal additives, such as Pt and Pd, on the heterogeneous isotope exchange reactions at the breeder-sweep gas interface was examined. The results indicate that the exchange reactions were considerably enhanced with the help of catalytic metals. In this work, the authors first examined the effect of the amounts of deposited catalytic active metal additives, such as Pt and Pd, on the heterogeneous isotope exchange reactions at the breeder-sweep gas interface. The results of this works indicate that the exchange reaction on the surface of Li4SiO4 is enhanced even if the amount of deposited Pd is as low as 0.015 %. It was also found that the deposition of 0.15 wt% of Pt enhances the exchange reaction rate. The authors also examined the effect of non-noble metal additive, such as Ni, on the heterogeneous isotope exchange reactions at the breeder-sweep gas interface. The results indicate that the exchange reactions were considerably enhanced with the help of Ni. Thus, it was found that Ni is also effective for the enhancement of the exchange reaction rate.