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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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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Latest News
Canada clears Darlington to produce Lu-177 and Y-90
The Canadian Nuclear Safety Commission has amended Ontario Power Generation’s power reactor operating license for Darlington nuclear power plant to authorize the production of the medical radioisotopes lutetium-177 and yttrium-90.
R. D. Werner, T. A. Eastwood
Nuclear Science and Engineering | Volume 21 | Number 1 | January 1965 | Pages 20-25
Technical Paper | doi.org/10.13182/NSE65-A21010
Articles are hosted by Taylor and Francis Online.
The thermal neutron-capture cross section of 1.0-year Ru106 has been determined from the yield of 22-min Rh107 formed in reactor irradiations. The average of four measurements is 0.146 barns. The experimental error is about ±7% but when systematic errors are included, largely in gamma-ray abundances from Ru106 and Rh107 decay, the uncertainty is about 30%. Cadmium-ratio measurements were made and the resonance-capture integral, including the 1/υ part, was found to be 2.0 ± 0.6 barns for an effective cadmium cutoff of 0.54 eV. These results are relative to a cobalt thermal neutron-capture cross section of 37.5 barns and total resonance integral of 72.7 barns. It has been assumed that neutron capture by Rh106, Ru107 and Rh107 is negligible, that the cross section of Ru106 in the thermal region has a 1/υ dependence and that the neutron spectrum is 1/E in the resonance region.