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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.
G. T. Chapman, W. R. Burrus
Nuclear Science and Engineering | Volume 34 | Number 2 | November 1968 | Pages 169-180
Technical Paper | doi.org/10.13182/NSE68-A19542
Articles are hosted by Taylor and Francis Online.
Measurements of the pulse-height distribution of gamma rays observed as a function of position and angle in the water shield of the Bulk Shielding Reactor II, a water-moderated and water-cooled pool-type reactor with stainless steel clad fuel plates, have been transformed to gamma-ray energy flux spectra by a computer program which removed the effects of the spectrometer's nonunique pulse-height response and accounted for the energy variation of the spectrometer's efficiency. The results show that the photons above 5 MeV originate primarily from thermal-neutron capture in the components of the stainless steel. Gamma rays due to the 57Fe component were identified as those known to be at 5.91, 6.02, and 7.6 MeV. Others were due to 58Fe at 10.16 MeV, to 54Cr at 8.88 and 9.72 MeV, and to 59Ni at 8.53 and 8.99 MeV. Below 5 MeV the spectra consist of a strong contribution at 2.2 MeV from thermal-neutron capture in the hydrogen of the pool water, combined with a continuum presumably composed of prompt and delayed gamma rays following fission, lower energy components in the capture spectra from the stainless steel, scattering in the reactor or shield, and other lesser sources.
