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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
Latest News
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Masabumi Nishikawa, Nobuyuki Nakashio, Toshiharu Takeishi, Satoshi Matsunaga, Kiyoteru Kuroki
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1233-1238
Tritium Properties and Interaction with Material | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST28-1233
Articles are hosted by Taylor and Francis Online.
Sorption behavior of tritium to isotropic graphite is discussed including solubility, diffusivity in the bulk of isotropic graphite and sorption capacity of hydrogen isotopes on the surface of isotropic graphite. The solubility and the diffusion coefficient of hydrogen isotopes in the graphite are obtained using the breakthrough method in the temperature range of 673–1273K and the activation energy of diffusivity is about 100kJ/mol. The sorption capacity of tritium on the graphite surface is also obtained by the breakthrough method using tritiated water in nitrogen gas flow. Tritium is captured on the graphite surface by isotope exchange reaction between tritium in gas flow and hydrogen in hydroxyl group on the graphite surface.These hydrogen atoms in hydroxyl group can easily exchange with other hydrogen isotopes in gas flow though they cannot be easily released from the graphite by drying or evacuating.