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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Latest News
Recent surveys confirm high levels of U.S. nuclear support
Surveys have consistently indicated that public support in the United States for the use of nuclear energy has been increasing in recent years. Four recent surveys continue to suggest that near-record-high numbers of Americans support nuclear energy. However, the survey results differ—sometimes widely—in the details of their findings.
R.S. Matsugu, J.C. Lehman, L. Borowski, P. Ladd
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1634-1639
Material and Tritium | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29575
Articles are hosted by Taylor and Francis Online.
A Tritium Filling Station to charge Inertial Confinement Fusion laser target microballoons with an equimolar mixture of tritium and deuterium has been designed, fabricated and pre-commissioned. The University of Rochester Laboratory for Laser Energetics will use the apparatus to produce targets for irradiation by their OMEGA glass laser. Microballoons are filled by diffusion through their walls. Each microballoon will hold about 5 millicuries of tritium in a deuterium-tritium mix at pressures of up to 15,000 kpa (2,200 psia). The maximum system tritium inventory is 10,000 curies.a Tritium and deuterium are stored in uranium beds. After retrieval from the beds, the deuterium-tritium mixture is assayed and transferred to the microballoon charging vessel via a unique palladium diffuser regulator. All components are housed in an inert atmosphere glove box with a getter-based purification system. The system design basis is presented with a description of mechanical and electrical components. Experience with the manufacture of tritium compatible equipment and subsequent system shop testing is described.