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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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Become a knowledge manager at UWC 2024
The American Nuclear Society is now accepting applications for knowledge managers to work during the 2024 Utility Working Conference and Vendor Technology Expo. This year’s UWC, “Nuclear Momentum: Advancing Our Clean Energy Future,” will be held August 4–7, 2024, at the JW Marriott Marco Island Beach Resort on Marco Island, Fla.=
Francesco Scaffidi-Argentina, Mario Dalle Donne, Claudio Ronchi, Claudio Ferrero
Fusion Science and Technology | Volume 33 | Number 2 | March 1998 | Pages 146-163
Technical Paper | doi.org/10.13182/FST98-A25
Articles are hosted by Taylor and Francis Online.
A new computer code, called ANFIBE (ANalysis of Fusion Irradiated BEryllium), has been developed to describe the most important processes (diffusion, gas precipitation, bubble coalescence, helium-bubble trapping, chemical trapping, etc.) thought to affect gas behavior and swelling in beryllium during fast neutron irradiation. The new model allows the prediction of helium and tritium redistribution, induced swelling, and release. The relevant effects occurring in irradiated beryllium under steady or transient temperature conditions have been considered from a microscopic (lattice and subgranular volume elements), structural (metallographic features of the material), and geometrical (specimen design parameters) point of view.The main results of this validation work represent the second part of the presentation of this model. The relevant beryllium properties published in the literature are presented and critically examined. The performance of the code is assessed by comparing the code predictions with a large set of published experimental data on swelling and gas release in beryllium under fast neutron irradiation.