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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.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
Standards Program
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
X-energy receives federal tax credit for TRISO fuel facility
Advanced reactor company X-energy has been awarded $148.5 million in tax credits under the Inflation Reduction Act for construction of its TRISO-X fuel fabrication facility in Oak Ridge, Tenn.
M. Zucchetti, F. Bombarda, B. Coppi
Fusion Science and Technology | Volume 61 | Number 1 | January 2012 | Pages 222-226
Fusion-Fission Hybrids and Transmutation | Proceedings of the Fifteenth International Conference on Emerging Nuclear Energy Systems | doi.org/10.13182/FST12-A13423
Articles are hosted by Taylor and Francis Online.
The foreseen future expansion of nuclear power would involve a solution to burn the long half-life transuranics (TRU) in the spent nuclear fuel discharged from LWRs. Moreover, high-energy neutrons can be very useful for many processes. The study addresses the development of a tokamak neutron source for a hybrid fission-fusion demonstration experimental device, using Ignitor-based technologies. Ignitor is a proposed compact high magnetic field tokamak, aimed at reaching ignition in DT plasmas. A revision of its operating parameters, in order to act a as a suitable neutron source in a hybrid device, is discussed, and a new operating scenario is proposed. Features of the tokamak neutron source are illustrated and preliminary results are discussed. A two-phase project is described, in order to test an Ignitor-based neutron source and then implement an experimental device for demonstration of technical feasibility of TRU transmutation.