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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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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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New laws offer nuclear industry incentives for existing power plant uprates
This year, the U.S. nuclear industry received a much-needed economic boost that could help preserve operating nuclear power plants and incentivize upgrades that extend their lifespan and power output.
Signed into law in 2022, the Inflation Reduction Act offers production tax credits (PTCs) for existing nuclear power plants and either PTCs or investment tax credits (ITCs) for new carbon-free generation. These credits could make power uprates—increasing the maximum power level at which a commercial plant may operate—a much more appealing option for utilities.
J. Devooght, E. H. Mund, B. Arien, A. Siebertz
Nuclear Science and Engineering | Volume 88 | Number 2 | October 1984 | Pages 191-199
Technical Note | doi.org/10.13182/NSE84-A28403
Articles are hosted by Taylor and Francis Online.
The numerical results that have been obtained for various reactor characteristics using the generalized quasi-static approximation for the study of fast reactor transients are analyzed. This approximation leads to a set of coupled nonlinear mixed boundary initial value problems for “amplitude” and “shape” neutron fluxes that are solved with a Newton-successive over-relaxation algorithm. Some details are given on the time integration module. Comparisons are established with the results obtained by other codes.
