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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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.
J. K. Dickens
Nuclear Science and Engineering | Volume 54 | Number 2 | June 1974 | Pages 191-196
Technical Note | doi.org/10.13182/NSE74-A23407
Articles are hosted by Taylor and Francis Online.
Interactions of neutrons with titanium have been studied by measuring gamma-ray-production cross sections. For a sample of natural titanium, spectra were obtained for incident-mean-neutron energies, En = 4.9, 5.4, and 5.9 MeV with gamma-ray detector systems utilizing coaxial Ge(Li) detectors. Nearly monoenergetic neutrons were obtained from the D(d,n) reaction using deuterons obtained from the (pulsed) Oak Ridge National Laboratory 5-MV Van de Graaff accelerator. Time of flight was used with the detector to discriminate against pulses due to neutrons and background radiation. Gamma-ray identification was aided by obtaining several spectra for samples enriched in the isotopes 46 Ti and 48Ti, and new information on the level structures of these two isotopes was obtained. Absolute differential cross sections for production of gamma rays were obtained and are reported. These cross sections have been compared, where possible, with previous (n,n’) measurements and with cross sections derived from the current ENDF/B evaluation.