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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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
Penn State and Westinghouse make eVinci microreactor plan official
Penn State and Westinghouse Electric Company are working together to site a new research reactor on Penn State’s University Park, Pa., campus: Westinghouse’s eVinci, a HALEU TRISO-fueled sodium heat-pipe reactor. Penn State has announced that it submitted a letter of intent to host and operate an eVinci reactor to the Nuclear Regulatory Commission on February 28 and plans to engage with the NRC on specific siting decisions. Penn State already boasts the Breazeale reactor, which began operating in 1955 as the first licensed research reactor at a university in the United States. At 70, the Breazeale reactor is still in operation.
Moses A. Greenfield, Roscoe L. Koontz, Alan A. Jarrett
Nuclear Science and Engineering | Volume 4 | Number 4 | October 1958 | Pages 563-569
Technical Paper | doi.org/10.13182/NSE58-A28832
Articles are hosted by Taylor and Francis Online.
The method for computing absolute thermal neutron flux from measurements made with activated indium foils is described. By combining data from the counting rate of indium foils in 2π proportional counters with appropriate corrections for foil weights and neutron effects, the thermal flux is expressed in terms of σO, the thermal absorption cross section of In115. This procedure may be used by laboratories which do not have access to a standard graphite pile or to a standard neutron source. This method has an estimated error of less than 5% which is a function of the accuracy with which it is possible to determine the various correction factors for beta counting. A possible fixed error in the value of σO can easily be corrected for and incorporated into the methods used.
