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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.
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.
Bal Raj Sehgal
Nuclear Science and Engineering | Volume 34 | Number 3 | December 1968 | Pages 251-262
Technical Paper | doi.org/10.13182/NSE68-A21090
Articles are hosted by Taylor and Francis Online.
Analysis of the nearly homogeneous enriched uranium-graphite critical assemblies described in the preceding paper by Phelps and Weinstock are reported in this paper. These assemblies are characterized mainly by their high leakage rate, and two methods are used for estimating the leakage: 1) the conventional B1 approximation method and 2) the moments method using Monte Carlo calculations for the moments of the slowing down distribution. It is found that the B1 approximation describes the leakage effects quite accurately. Most of the cross sections used in the calculations are from the recent evaluated nuclear data file (ENDF/B). Results of calculations for keff, neutron lifetimes, and foil activation ratios are generally in excellent agreement with the measurements.
