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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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.
John T. Mihalczo
Nuclear Science and Engineering | Volume 47 | Number 3 | March 1972 | Pages 290-301
Technical Paper | doi.org/10.13182/NSE72-A22415
Articles are hosted by Taylor and Francis Online.
A series of dynamic measurements has been performed with a multiplying assembly in which a rotating beryllium reflector (worth 4.8 dollars in reactivity) moved past an unreflected core surface ∼60 times/sec at a speed of 264 m/sec. A pulse of 14.1-MeV neutrons was injected into the assembly each time the rotating reflector attained a position for which the reactivity of the assembly was maximum. The time distribution of neutrons after the injection of the pulse was measured in the core and adjacent to a 10.16- × 10.16- × 3.81-cm polyethylene scatterer which provided a pulse of thermal leakage neutrons. The maximum prompt-neutron multiplication of the assembly, which was reflected with iron on all sides but one and contained 58.6 kg of highly enriched uranium metal at delayed criticality, was varied from 75 to 285 by fuel loading changes. This assembly with a maximum prompt-neutron multiplication of 285 produced fast-neutron pulses with a width at half-maximum of 3.9 μsec, with a peak-to-minimum ratio of 12,400 and with 80% of the power in the pulse. These pulses, when thermalized by the scatterer, were broadened to a width at half-maximum of 20.9 μsec with a peak-to-minimum power ratio of 1590. The number of thermal neutrons leaking from the outer surface of the scatterer was 3.3 × 10−5 n/(cm2 fission).