ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
NRC cuts fees by 50 percent for advanced reactor applicants
The Nuclear Regulatory Commission has announced it has amended regulations for the licensing, inspection, special projects, and annual fees it will charge applicants and licensees for fiscal year 2025.
L. Forman, F. A. White
Nuclear Science and Engineering | Volume 28 | Number 1 | April 1967 | Pages 139-143
Technical Paper | doi.org/10.13182/NSE67-A18677
Articles are hosted by Taylor and Francis Online.
The thermal-neutron capture cross section of 147Sm has been measured by the mass spectrometric determination of the number of 148Sm atoms formed by neutron capture. Samples of high isotopic purity were irradiated in a well-thermalized neutron spectrum for which the time-integrated neutron flux and effective neutron temperature were monitored by the burnup in 149Sm and 157Gd. A thermal-neutron capture cross section value of 75 ± 11 b was obtained from a post-irradiation 148Sm/ 147Sm ratio of 0.00025 ± 8%, at an effective neutron temperature of 127 ± 13°C.
