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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
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
A good narrative for nuclear power
Melbye
During an interview for Kitco News at the 2025 Prospectors & Developers Association of Canada (PDAC) Convention, held in Toronto in early March, the chief executive of British Columbia–based Uranium Royalty Corp. noted, “I’ve never seen a better narrative around nuclear power [and] uranium.”
CEO Scott Melbye, who is also executive vice president of Texas-based Uranium Energy Corp. and has 41 years of experience in the uranium sector, added that nuclear energy has gone from stagnation or decline to a point where it may double by 2040.
J. Rapp, A. Lumsdaine, A. Aaron, T. M. Biewer, T. S. Bigelow, T. Boyd, J. B. O. Caughman, D. Curry, R. C. Duckworth, R. H. Goulding, A. Hussain, M. Kaufman, C. H. Lau
Fusion Science and Technology | Volume 79 | Number 8 | November 2023 | Pages 1113-1123
Research Article | doi.org/10.1080/15361055.2023.2168443
Articles are hosted by Taylor and Francis Online.
The Material Plasma Exposure eXperiment (MPEX) has completed its design phase. MPEX will be a unique facility to investigate plasma material interactions (PMIs) under fusion prototypic divertor conditions in steady state. This includes plasma exposure conditions expected in a fusion reactor divertor. Materials to be investigated will include solids, liquids, and neutron pre-irradiated materials. Electron and ion heating will allow for a large operational domain ranging from erosion-dominated PMI conditions to deposition-dominated PMI conditions. An overview of the final design for all MPEX systems is given. In particular, it is shown how mission-driven project requirements have led to detailed design choices with innovative solutions. Examples are the water-cooled helicon window, the electron cyclotron heating launcher, the target holder and manipulator, and the autonomous decouplers.