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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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Fusion Science and Technology
Latest News
Construction begins on Kairos’s fluoride salt–cooled test reactor
Earlier today, on a site in Oak Ridge, Tenn., that was formerly home to the K-33 Gaseous Diffusion Plant, Kairos Power marked the start of construction on its low-power demonstration reactor. Named Hermes, the 35-MWt test reactor claims status as the first Gen IV reactor to be approved for construction by the Nuclear Regulatory Commission and the first non–light water reactor to be permitted in the United States in more than 50 years.
A. N. Perevezentsev, L. A. Bernstein, L. A. Rivkis, I. G. Prykina, V. V. Aleksandrov, I. A. Ionessian, M. I. Belyakov, I. B. Kuprianov
Fusion Science and Technology | Volume 72 | Number 1 | July 2017 | Pages 1-16
Technical Paper | doi.org/10.1080/15361055.2016.1273659
Articles are hosted by Taylor and Francis Online.
The subject of this study is the evaluation of tritium outgassing and removal from metals such as tungsten, beryllium, stainless steel, and copper alloy. In addition, a composite sample assembled from tungsten, copper alloy, and stainless steel was also studied. Samples of individual materials and composite samples were of thicknesses and compositions representing the internal components of the ITER vacuum vessel. The samples of materials were loaded with tritium by exposure to a gaseous tritium-deuterium mixture (about 1:1) at a temperature of 473 K and a pressure of about 0.05 MPa. The rate of outgassing was measured at temperatures of about 295, 308, and 323 K under static or dynamic atmospheres either of ambient air or dry air or argon. The study allows recommendation of conditions for storage of in-vessel components and reduction of the rate of tritium outgassing. The metals’ samples were also subject to study of tritium removal by thermal desorption under purge with argon containing 5 vol % of hydrogen. The study has demonstrated that this detritiation procedure allows for removal of large portions of the tritium inventory and substantial reduction in tritium outgassing rates.