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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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
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.
Tatsuhiko Uda, Takahiko Sugiyama, Yamato Asakura, Kenzo Munakata, Masahiro Tanaka
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 480-483
Technical Paper | Tritium Science and Technology - Containment, Safety, and Environment | doi.org/10.13182/FST05-A970
Articles are hosted by Taylor and Francis Online.
Recovery of tritium released into a working area in a nuclear fusion plant is a key issue of safety. The catalytic oxidation of isotopic hydrogen including tritium is a conventional method for removing tritium from the air of the room. If a tritium release accident occurs in the fusion plant, large volumes of air should be processed by the air cleanup system. The system should be designed to be able to process the gas with high volumetric velocity. However, the high throughput of air causes pressure drop in the catalyst bed, which results in high load to the pumping system. In this study, and their applicability of honeycomb catalysts to the tritium recovery system was examined. The honeycomb catalyst has an advantage in terms of pressure drop, which is far less than that in conventional particle-packed catalyst beds. The experiments on honeycomb catalysts such as cordierite and Al-Cr-Fe metal alloy indicate their preferable oxidizing performance. Particularly, the metal honeycomb has an advantage for hydrogen gas oxidization at room temperature because it is expected to be less affected memory effect by tritium contamination. Thus, these honeycomb catalysts are applicable to the tritiated gases recovery system with high performance.