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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Nuclear Science and Engineering
July 2025
Nuclear Technology
June 2025
Fusion Science and Technology
Latest News
Countering the nuclear workforce shortage narrative
James Chamberlain, director of the Nuclear, Utilities, and Energy Sector at Rullion, has declared that the nuclear industry will not have workforce challenges going forward. “It’s time to challenge the scarcity narrative,” he wrote in a recent online article. “Nuclear isn't short of talent; it’s short of imagination in how it attracts, trains, and supports the workforce of the future.”
G. Velarde, J.M. Aragonés, M.C. Gonzalez, P. Hernén, J.J. Honrubia J.L. Hortal, J.M. Martínez-Val, E, Mínguez, J.L. Ocaña, J.M. Perlado, J.M. Santolaya, J. Sanz
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 1850-1855
Inertial Confinement Fusion Reactor | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A40030
Articles are hosted by Taylor and Francis Online.
This article discusses the effect of different potential spectra of neutrons leaking from an inertial confinement fusion (ICF) pellet on integral parameters characterizing the blanket performance. We have compared time dependent and steady state neutron calculations to determine the neutron and gamma spectra from the target. Results show, that assuming a fuel burnup-average ρR parameter,<ρR>b, in the steady state method, realistic spectra can be obtained. The influence of the fuel <ρR>b, ρΔR pusher parameter as well as that of the gammas exploding from the target, on the chamber response has been analyzed.
