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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
G7 pledges support for nuclear at Italy meeting
The Group of Seven (G7) recommitted its support for nuclear energy in the countries that opt to use it at a Ministerial Meeting on Climate in Italy last month.
In a statement following the April meeting, the group committed to support multilateral efforts to strengthen the resilience of nuclear supply chains, referencing the goal set by 25 countries during last year’s COP28 climate conference in Dubai to triple global nuclear generating capacity by 2050.
Stephen N. Gilliam, Jamie B. Coble, Steven E. Skutnik
Nuclear Science and Engineering | Volume 195 | Number 9 | September 2021 | Pages 965-976
Technical Paper | doi.org/10.1080/00295639.2021.1883399
Articles are hosted by Taylor and Francis Online.
In this paper, we investigate the possibility of plutonium quantification within the electrorefiner vessel of an electrochemical separation facility via the use of the (α,n) neutron signature from dissolved actinides. As a potential alternative means to traditional spontaneous fission tracking, such an analysis may provide a more reliable tracking capability of plutonium within systems that produce a mixed matrix sample that yields a large (α,n) source term relative to that of spontaneous fission. This assessment includes an evaluation and breakdown of nuclides within the refining unit to differentiate the source of neutrons and then the ratio between (α,n) emissions to total neutron emissions given a range of fuel parameters. Next, we provide an assessment of the origin of (α,n) neutrons in relation to multiple isotopes of plutonium to determine the potential of a direct tracking method. Preliminary results indicate that the (α,n) contribution for electrochemical systems is much higher than in its aqueous counterpart and rivals spontaneous fission yield in terms of magnitude. Furthermore, 238Pu is shown to be a main contributor to the (α,n) yield for the fuel examined in this study.