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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
NEA panel on AI hosted at World Governments Summit
A panel on the potential of artificial intelligence to accelerate small modular reactors was held at the World Governments Summit (WGS) in February in Dubai, United Arab Emirates. The OECD Nuclear Energy Agency cohosted the event, which attracted leaders from developers, IT companies, regulators, and other experts.
Donald L. Smith, J. W. Meadows, Frank F. Porta
Nuclear Science and Engineering | Volume 78 | Number 4 | August 1981 | Pages 420-424
Technical Note | doi.org/10.13182/NSE81-A21378
Articles are hosted by Taylor and Francis Online.
An experimental facility has been developed for short-half-life neutron activation studies. Sample material is transported between the irradiation position and the counting position by a constant-velocity cog belt. This facility has been used to measure the 53Cr(n,p)52V cross section relative to the 52Cr(n,p)52V cross section below 9.4 MeV, using elemental chromium metal as a sample material. The measured ratios and previously reported cross-section information for the 52Cr(n,p)52V have been used to derive values for the 53Cr(n,p)53V cross section. The 235U thermal-neutron fission spectrum average has been calculated from the differential results, and comparison is made with reported integral data.
