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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
N. N. Kaushal, B. K. Malaviya, M. Becker, E.T. Burns, E. R. Gaerttner
Nuclear Science and Engineering | Volume 49 | Number 3 | November 1972 | Pages 330-348
Technical Paper | doi.org/10.13182/NSE72-A22546
Articles are hosted by Taylor and Francis Online.
Fast neutron spectra in a cuboidal assembly of uranium depleted in the 235U isotope have been measured for the purpose of providing integral checks on cross-section data pertinent to fast reactor development. Spectral measurements have been made at three different radial distances and several different angles, and cover an energy range from 10 keV to 10 MeV. The experimental spectra are compared with Sn transport calculations involving ENDF/B-I, ENDF/B-II, KEDAK (from Karlsruhe) files, and a multigroup set from Argonne National Laboratory and conclusions are drawn as to the adequacy of these data for predicting measured spectra. Extensive use is made of the continuous slowing down theory to pinpoint specific areas of uncertainty in the cross-section data. From a comparison of the experimental spectra with the calculations, it is concluded that the neutron capture cross-section data in the 238U ENDF/B files should be lowered by about 10% in the range 10 to 40 keV. Additionally, the slowing down effectiveness of inelastic scattering in the range 40 to 500 keV should be lowered by about 25%. Discrepancies among various data files are also observed in the inelastic slowing down effectiveness in the range 1 to 2 MeV.
