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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
Standards Program
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
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.
H. O. Menlove, R. A. Forster, J. L. Parker, Darryl B. Smith
Nuclear Technology | Volume 20 | Number 2 | November 1973 | Pages 124-133
Technical Paper | Analysis | doi.org/10.13182/NT73-A31348
Articles are hosted by Taylor and Francis Online.
A hybrid assay system utilizing both active and passive techniques has been built for the measurement of the plutonium fissile content in fast-breeder-reactor-type fuel pins. A moderated 252Cf source (∼600 µg) is used for the neutron interrogation of the fuel rods, and the fissile content is then determined by counting the high-energy delayed gamma rays resulting from the induced fission reactions. Neutron transport calculations using both Sn and Monte Carlo techniques were used to design the 252Cf neutron tailoring assembly to give an intense fast-neutron irradiation, as well as a high fissile/fertile fission ratio. In addition to the total fissile active assay, pellet-to-pellet uniformity is determined simultaneously by counting the lower energy passive gamma rays from the fuel using the same NaI detectors. The complete assay system, which includes automated fuel-rod handling and data reduction, is being used for in-plant measurements of Fast Flux Test Facility fuel pins.
