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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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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.
Robert E. Rothe
Nuclear Science and Engineering | Volume 35 | Number 2 | February 1969 | Pages 267-276
Technical Paper | doi.org/10.13182/NSE69-A21142
Articles are hosted by Taylor and Francis Online.
Critical parameters are reported for an essentially unreflected system containing uranium solution and a fixed neutron poison. The uranium solution contained 450.8 g of uranium per liter. The uranium was enriched to 93.19 wt% 235U. The fixed poison was natural boron contained in stainless steel plates and comprised 1.02 wt% of the plates. The total boron content was varied on successive runs by changing the number of plates. The plates were arranged along parallel chords of the 106.6-cm-diam cylindrical experimental tank; they were approximately uniformly spaced. Three types of measurements are reported. The first type provides data on an unpoisoned slab. In the second type, the uranium solution height at criticality was less than the height of the plates (119 cm) and provided data on a poisoned solution cylinder. When the boron concentration was 16.41 g/liter, the cylinder was sub-critical even if infinitely long. The third type of measurement, where the critical uranium solution height exceeded the plate height, allowed an evaluation of the interaction between an unpoisoned slab and a highly poisoned region. The highest boron concentration measured was 20.62 g/liter. The experimental data are compared with results from neutron transport and diffusion computer codes. Computer results also provide asymptotic values for critical parameters not amenable to measurement because of apparatus limitations. Finally, the computer was used to extend the applicability of the data to more general systems.