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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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Nuclear Technology
Fusion Science and Technology
October 2025
Latest News
DOE’s latest fusion energy road map aims to bridge known gaps
The Department of Energy introduced a Fusion Science & Technology (S&T) Roadmap on October 16 as a national “Build–Innovate–Grow” strategy to develop and commercialize fusion energy by the mid-2030s by aligning public investment and private innovation. Hailed by Darío Gil, the DOE’s new undersecretary for science, as bringing “unprecedented coordination across America's fusion enterprise” and advancing President Trump’s January 2025 executive order, on “Unleashing American Energy,” the road map echoes plans issued by the DOE’s Office of Fusion Energy Sciences (FES) in 2023 and 2024, with a new emphasis on the convergence of AI and fusion.
The road map release coincided with other fusion energy events held this week in Washington, D.C., and beyond.
H. E. McCoy, R. E. Gehlbach
Nuclear Technology | Volume 11 | Number 1 | May 1971 | Pages 45-60
Technical Paper | Material | doi.org/10.13182/NT71-A30901
Articles are hosted by Taylor and Francis Online.
The variation of the postirradiation creep-rupture properties with irradiation temperature has been evaluated for air- and vacuum-melted Hastelloy-N. The air-melted material was high in silicon and formed a stable carbide of the M6C type. The properties of this material were not dependent upon the irradiation temperature over the range studied. The vacuum-melted alloys formed a M2C-type carbide whose size and morphology depended markedly upon the irradiation temperature. When the carbides were finely dispersed by irradiation at about 650°C, the postirradiation properties were equivalent to those of the air-melted material. Irradiation at about 760°C resulted in coarser dispersions of the M2C carbide and inferior postirradiation properties.
