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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.
Kazuhiro Kobayashi, Takumi Hayashi, Hirofumi Nakamura, Toshihiko Yamanishi, Yasuhisa Oya, Kenji Okuno
Fusion Science and Technology | Volume 52 | Number 3 | October 2007 | Pages 696-700
Technical Paper | The Technology of Fusion Energy - Tritium, Safety, and Environment | doi.org/10.13182/FST07-A1571
Articles are hosted by Taylor and Francis Online.
In a fusion reactor of high safety and acceptability, safe confinement of tritium is one of key issues for the fusion reactor. Tritium should be well-controlled and not excessively released to the environment and to prevent workers from excess exposure. Especially, the hot cell and tritium facilities of ITER will use various construction materials such as the organic materials. The hot cell is maintained in the dry atmosphere very much, and the maintenance of the apparatus contaminated by high concentration tritium is assumed. Therefore, the hot cell may be contaminated by high concentration tritium. Since the epoxy paint which will be used as a paint on the wall of the hot cell was contaminated by tritium compared with metal material, it is very important to study the efficient decontamination of the epoxy paint from a viewpoint of the protection the excess exposure of the workers. For tritium decontamination processes, so-called 'soaking' effect is important. This effect is based on sorption of tritiated water vapor on the materials and subsequent desorption from them. Therefore, in order to develop for the optimal decontamination technique, the decontamination experiment was carried out as a function of water vapor concentration in the purge gas (N2) for epoxy paint, acrylic resin and butyl rubber. As the result, the desorption rate for the organic materials was evaluated by purging gas of N2, and then furthermore, the residual tritium on the organic materials was quickly removed by adding water vapor in purging gas. The effect of adding water vapor was found on the decontamination for the organic materials.