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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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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.
G. D. Wait
Nuclear Technology | Volume 4 | Number 6 | June 1968 | Pages 440-447
Technical Paper and Note | doi.org/10.13182/NT68-A26370
Articles are hosted by Taylor and Francis Online.
A high-sensitivity dosimeter system was developed to measure low gamma-ray dose rates in the presence of neutrons. The detector is a liquid scintillator that employs hexafluorobenzene (C6F6) as a solvent and is practically hydrogen free. The energy absorbed in the scintillator is determined directly by counting the analog-to-digital converter pulses of a multichannel analyzer in a fast scaler. The ratio of energy absorbed to air exposure dose was measured for incident gamma energies of 0.06 MeV (241Am), 0.66 MeV (137Cs), 1.25 MeV(60Co), and 4.43 MeV (241AmBe) and gave an average deviation of 3.5% from a constant ratio of energy absorbed to air exposure. A Monte Carlo computer program was written to determine the response of the scintillator to a broader range of gamma-ray energies. This indicated that the ratio of the energy absorbed to the air exposure would vary within the limits of ±10% from 50keV to 10 MeV. The response to fast neutrons also was measured and compared with calculations which showed that the major component in the neutron response was produced by β− decay following the (n,α) reaction in 19F. For the broad spectrum of incident fast neutrons (up to 11.5 MeV) from a 241AmBe source, the neutron response of the dosimeter was found to be < 8% of its response to the comparable flux of 4.43 MeV gamma rays from the source.