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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.
Takashi Kiguchi, Shigehiro An, Akira Oyama
Nuclear Science and Engineering | Volume 43 | Number 3 | March 1971 | Pages 328-340
Technical Paper | doi.org/10.13182/NSE71-A19979
Articles are hosted by Taylor and Francis Online.
The energy modal synthesis method is applied to the computation of the neutron-multiplication factor, the sodium-void coefficient, and the spatial-power distribution of an idealized fast reactor configuration. The method is formulated by means of the variational principle and the error estimator is introduced by the expansion technique of the trial functions in the eigenfunction series. In the space-independent case, the sodium-void coefficient and its error are obtained very accurately by the linear combination of two modes, and the optimal two modes are chosen by the physical consideration. In the one-dimensional case, the continuous-type and the discontinuous-type energy modal synthesis method are formulated. In both cases the infinite-medium spectra and some supplementary modes are used as the trial energy modes. The results of a few-mode synthesis give a good estimate of the reactor parameters, and the error can be evaluated successfully by the error estimator.
