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Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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.”
M. Aristova, C. A. Gentile
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 475-477
IFE Drivers and Chambers | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8948
Articles are hosted by Taylor and Francis Online.
An important technical and economic consideration in designing the prospective direct drive inertial fusion energy (IFE) reactor is the determination of a suitable mechanism for tritium breeding from neutrons produced in the initial reaction. A comprehensive review has been undertaken to determine the optimal breeding material, examining several candidate compounds. These include ceramic breeding pebbles as well as liquid 83Pb-17Li (Pb-Li) and (LiF)2BeF2 (FLiBe). In this study, the compounds are evaluated based on chemical and physical properties, structural requirements, feasibility, hazards, and costs of application. Preliminary results seem to indicate that, of the liquid breeding materials, FLiBe may be the more practical option, due to its mechanical feasibility and the relative projected efficiency of blanket design. Likewise, lithium metatitanate (Li2TiO3) appears to be a viable ceramic material. However, much remains to be investigated, particularly the properties of breeder and structural materials in the specific conditions of a reactor. Further work in this area will require theoretical modeling as well as practical trials, currently planned in other progenitor reactor designs. This paper will present the results of the analysis of these candidate breeder materials.
