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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.
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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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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.
V. V. Verbinski, M. S. Bokhari, J. C. Courtney, and G. E. Whitesidestt
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 283-298
Technical Paper | doi.org/10.13182/NSE67-A18268
Articles are hosted by Taylor and Francis Online.
The spectral intensity of the fast-neutron flux penetrating a water medium was measured for two configurations: a large-source, poor-geometry arrangement; and a small-source, almost-good-geometry configuration., In the large-source experiment, the spectral intensity of the angular flux was obtained at six positions in the water shield of a pool-type reactor and for as many as three angles at each position. In addition to the measurements, the spectral shape and the absolute intensity of angular flux in the shield were calculated. In conjunction with this, the absolute neutron source density was mapped throughout the reactor volume and the distribution along the reactor center line was used as input to two neutron-transport calculations that were carried out for a onedimensional, spherical geometry., In the small-source experiment, a 2-cm-thick lead target irradiated with short bursts of 33-MeV electrons provided a source of photoneutrons with approximately a fission spectrum at a distance of 40 cm from water slabs of various thicknesses. This distance, together with the large separation of slab and detector and a small-aperture collimator, approximated a good-geometry arrangement for measurements of neutrons leaking normally from the slab. Consequently, these leakage spectra were very sensitive to total neutron cross sections and a distinct peak was observed at 5 to 7.5 MeV. This peak was not at first reproduced by transport calculations that used the measured source spectrum as input; however, when the neutron total cross sections of oxygen were updated with relatively recent high-resolution data, the agreement both in spectral shape and in attenuation (the latter determined from sulfur-activation ratios) was noticeably improved.