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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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A webinar, and a new opportunity to take ANS’s CNP Exam
Applications are now open for the fall 2025 testing period for the American Nuclear Society’s Certified Nuclear Professional (CNP) exam. Applications are being accepted through October 14, and only three testing sessions are offered per year, so it is important to apply soon. The test will be administered from November 12 through December 16. To check eligibility and schedule your exam, click here.
In addition, taking place tomorrow (September 19) from 12:00 noon to 1:00 p.m. (CDT), ANS will host a new webinar, “How to Become a Certified Nuclear Professional.” More information is available below in this article.
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.
