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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
Moltex demonstrates its WATSS fuel recycling process
Advanced reactor company Moltex Energy Canada said it has successfully validated its waste to stable salt (WATSS) process on used nuclear fuel bundles from an unnamed Canadian commercial reactor through hot cell experiments conducted by Canadian Nuclear Laboratories.
L. M. Howe, R. E. Jervis, T. A. Eastwood
Nuclear Science and Engineering | Volume 12 | Number 2 | February 1962 | Pages 185-189
Technical Paper | doi.org/10.13182/NSE12-2-185
Articles are hosted by Taylor and Francis Online.
Aluminum-gold alloy wire of very uniform cross section and composition has been made for the preparation of neutron flux monitors. Because the wire is uniform, a device to cut it into pieces of equal length can be used for the rapid preparation of flux monitors and the need to weigh individual monitors can thus be avoided. Homogeneity of composition was achieved mainly by rolling and annealing, and the effectiveness of each step was assessed by neutron-activation analysis. The gold content of the final product (wire 0.018 in. diameter) was also determined by activation analysis and was found to be 0.0985 ± 0.0020 atom %. Thermal-neutron self-shielding in this wire is negligible and cadmium ratio experiments show that resonance-neutron self-shielding amounts to about 2.5%.