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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.
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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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Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Alex Aimetta, Nicolò Abrate, Sandra Dulla, Antonio Froio
Fusion Science and Technology | Volume 78 | Number 4 | May 2022 | Pages 275-290
Technical Paper | doi.org/10.1080/15361055.2021.2003151
Articles are hosted by Taylor and Francis Online.
Neutronic modeling of fusion machines requires a detailed representation of their complex geometry in order to properly evaluate various parameters of interest such as energy deposition and tritium production in the breeding blanket. In this work, the neutronics of the Affordable, Robust, Compact (ARC) fusion reactor is modeled with the Monte Carlo particle transport code Serpent developed at VTT Technical Research Centre of Finland as an alternative to other, more established, tools in the fusion community such as the Monte Carlo N-Particle Transport (MCNP) code. The tritium breeding ratio (TBR) and the power deposited by neutrons and photons inside the breeding blanket of ARC are evaluated. Considerations related to activation of materials and to neutron shielding are not taken into account. As a first step, estimations have been obtained adopting a spatially uniform neutron source inside the plasma chamber. A second set of calculations has been performed considering a nonuniform source that takes into account a more realistic neutron generation distribution, with higher values at the center of the plasma and reduced rates toward the plasma edge. The results obtained with Serpent have been compared with available literature values for the TBR and the power deposition, confirming that Serpent can be considered a suitable alternative code for the neutronic analysis of fusion reactors like ARC. The TBR presented in this paper (1.0853) is in good agreement with the value found in the literature, with a relative difference of 0.49%. The total power deposition has a maximum relative difference of 12% for the components of interest in the present work.