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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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.
S. H. Hayes, P. Stoler, J. M. Clement, C. A. Goulding
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 243-247
Technical Paper | doi.org/10.13182/NSE73-A28977
Articles are hosted by Taylor and Francis Online.
A measurement of the total neutron cross sections of 238 U was made using the Rensselaer Polytechnic Institute electron LINAC. The operating electron energy was about 60 MeV, and the beam burst width was 20 nsec. The neutron energies were determined using the time-of-f light technique with an overall resolution of 0.1 nsec/m. The cross sections are presented from 0.8 to 30.0 MeV; the cross-section curve is smooth in this region, and the averaged data have a statistical precision of 1%. The data reported here have been compared with the ENDF/B-III file. The disagreements are within 2% over the energy range 0.8 to 15 MeV. In addition, the experimental cross sections were fit using coupled channel code JUPITOR to obtain optical model and deformation parameters.
