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Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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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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Molten salt research is focus of ANS local section presentation
The American Nuclear Society’s Chicago–Great Lakes Local Section hosted a presentation on February 27 on developments at the molten salt research reactor at Abilene Christian University’s Nuclear Energy Experimental Testing (NEXT) Lab.
A recording of the presentation is available on the ANS website.
John T. Mihalczo, Victor I. Neeley
Nuclear Science and Engineering | Volume 13 | Number 1 | May 1962 | Pages 6-11
Technical Paper | doi.org/10.13182/NSE62-A26121
Articles are hosted by Taylor and Francis Online.
The infinite medium neutron multiplication factor, k∞, of a mixture of 92.1 wt% UF4 and 7.9 wt% paraffin has been measured both in the Physical Constants Testing Reactor at the Hanford Atomic Products Operation and in critical experiments at the Oak Ridge National Laboratory. The density of the mixture is 4.5 gm/cc and the U235 enrichment of the uranium is 2.0 wt%, resulting in an H:U235 atomic ratio of 195. The values of k∞ 0.013 and 1.197 ± 0.013 and 1.197 ± 0.015, respectively. In the analysis of the critical experiments a two group model was assumed for the nonleakage probability. The neutron age to thermal was determined from buckling perturbation measurements as 43.1 ± 3.4 cm2. The critical buckling was measured to be (4344 ± 65) × 10−6 cm−2, the bare extrapolation distance 2.7 ± 0.3 cm, and the fast fission factor 1.039 ± 0.004. Within the experimental error, the values of k∞ from critical experiments at ORNL and from the PCTR at HAPO agree.