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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
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.
