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Division Spotlight
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.
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
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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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.
Marion L. Stelts, John D. Anderson, Luisa F. Hansen, Ernest F. Plechaty, Calvin Wong
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 53-60
Technical Paper | doi.org/10.13182/NSE71-A22335
Articles are hosted by Taylor and Francis Online.
The validity of the neutron Monte Carlo transport code, SORS, has been established for the transport of fast neutrons through water by comparing the measured time spectra of neutrons from spherical water targets of 1.0 and 1.8 mean-free-paths radii with the calculations. The energy degradation and spatial spreading of a beam of 14-MeV neutrons through a thickness of water comparable to the thickness of a human body were calculated for use in the design of experiments to treat cancer tumors with 14-MeV neutron beams. For use in shielding applications, further calculations have also been made of the transport of neutrons from an isotropic source of 14-MeV neutrons located at the center of spherical water shields having radii from 0.5 to 7.0 mfp.
