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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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Remembering Charles E. Till
Charles E. Till
Charles E. Till, an ANS member since 1963 and Fellow since 1987, passed away on March 22 at the age of 89. He earned bachelor’s and master’s degrees from the University of Saskatchewan and a Ph.D. in nuclear engineering from Imperial College, University of London. Till initially worked for the Civilian Atomic Power Department of the Canadian General Electric Company, where he was the physicist in charge of the startup of the first prototype CANDU reactor in Canada.
Till joined Argonne National Laboratory in 1963 in the Applied Physics Division, where he worked as an experimentalist in the Fast Critical Experiments program. He then moved to additional positions of increasing responsibility, becoming division director in 1973. Under his leadership, the Applied Physics Division established itself as one of the elite reactor physics organizations in the world. Both the experimental (critical experiments and nuclear data measurements) and nuclear analysis methods work were internationally recognized. Till led Argonne’s participation in the International Nuclear Fuel Cycle Evaluation (INFCE), and he was the lead U.S. delegate to INFCE Working Group 5, Fast Breeders.
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.