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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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.
C. Lajeunesse, W. E. Moore, M. L. Yeater
Nuclear Science and Engineering | Volume 47 | Number 3 | March 1972 | Pages 349-364
Technical Paper | doi.org/10.13182/NSE72-A22420
Articles are hosted by Taylor and Francis Online.
The double-differential scattering cross section of polycrystalline natural uranium carbide (UC) has been measured for incident energies of 0.092, 0.135, and 0.159 eV. Inelastic scattering peaks corresponding to excitation energies of 0.013 and 0.045 eV were observed and are shown to belong to acoustic and optical modes of the UC lattice. A model has been developed using a normal mode analysis based on the Born and Von Kármán approximation, including noncentral forces and considering up to third-nearest neighbors. A theoretical scattering law has been derived based on this analysis. Resolution and multiple scattering effects have been calculated using a new Monte Carlo approach. After the application of these corrections, the double differential cross sections derived from the theoretical scattering law agree with the measurements. The variation of the specific heat with temperature is accurately predicted by the model. The total cross section was also measured for the energy range 0.006 to 3.5 eV. The Bragg peaks due to coherent scattering were resolved up to 0.05 eV. The total cross section calculated from our noncentral force model compares well with this measurement.