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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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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Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
W. Beyrich, G. Spannagel
Nuclear Technology | Volume 42 | Number 3 | March 1979 | Pages 337-342
Technical Paper | Analysis | doi.org/10.13182/NT79-A32190
Articles are hosted by Taylor and Francis Online.
If different laboratories using thermionic mass spectrometry determine in routine operation a 235U concentration of ≈0.7% in the same sample material, their measurement results deviate by at least 0.8% (relative) in ≈50% of the cases. The application of gas mass spectrometry reduces this deviation to 0.1 or 0.05%, the more favorable value being obtained by measurements in which the same reference material is used by all laboratories. These results were obtained by application of an empirical evaluation procedure that, contrary to the usual statistical tools, is not restricted to homogeneous data material. The data were taken from two interlaboratory evaluation programs performed recently on the isotopic abundance determination of 235U in uranium hexafluoride by mass spectrometry.