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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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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
C. Konno, Y. Oyama, Y. Ikeda, K. Kosako, H. Maekawa, T. Nakamura, A. Kumar, M.Z. Youssef, M.A. Abdou, E.F. Bennett
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1885-1890
Neutronic | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29618
Articles are hosted by Taylor and Francis Online.
A pseudo line DT neutron source has been realized by moving an experimental assembly with respect to a point DT source in the Phase-III experiment of JAERI/USDOE collaborative program on fusion blanket neutronics. In order to examine characteristics of the pseudo-line source made by two types of operational modes, source term experiments were carried out. Neutron flux distribution above 10 MeV was measured by NE213 scintillator with stepwise source mode. The reaction rate distributions were also measured by activation foil technique with continuous source mode. The measured distributions were almost flat over central 1 m region of the simulated line source and agreed relatively with a simple calculation assuming the ideal line source. From these experimental results it was concluded that both modes worked successfully to obtain the pseudo-line source and could simulate well neutron flux distribution emitted from a finite length line source with small influence of reaction kinematics and target structure.