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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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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.
Darrell F. Newman
Nuclear Technology | Volume 15 | Number 2 | August 1972 | Pages 192-208
Technical Paper | Plutonium Utilization in Commercial Power Reactors / Reactor | doi.org/10.13182/NT72-A31145
Articles are hosted by Taylor and Francis Online.
The neutron multiplication factor, k∞, and relative reaction rates have been measured at room temperature in the Physical Constants Testing Reactor (PCTR) for a water-moderated lattice fueled with Zircaloy-clad UO2-PuO2 fuel rods. The plutonium content in different sets of fuel rods ranged from 0.9 to 2.5 wt% PuO2 in UO2. These experiments provide neutronics data for uniform lattices of mixed-oxide fuels which contain plutonium oxide distributed throughout the uranium oxide as finite-sized particles. The PuO2 particle sizes in different sets of fuel rods ranged between 0 and 328 µm in diameter. Knowledge of the effect that plutonium particle size has on neutron multiplication is important for the economic utilization of plutonium. An experiment-theory correlation provides a basis for assessing the adequacy of calculational techniques.