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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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How to talk about nuclear
In your career as a professional in the nuclear community, chances are you will, at some point, be asked (or volunteer) to talk to at least one layperson about the technology you know and love. You might even be asked to present to a whole group of nonnuclear folks, perhaps as a pitch to some company tangential to your company’s business. So, without further ado, let me give you some pointers on the best way to approach this important and surprisingly complicated task.
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.
