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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
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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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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.
S. Das
Nuclear Science and Engineering | Volume 122 | Number 3 | March 1996 | Pages 344-358
Technical Paper | doi.org/10.13182/NSE96-A24169
Articles are hosted by Taylor and Francis Online.
The method of point reactor kinetics in conjunction with the new concepts of delayed spectrum factor and beta growth factor is used to calculate the sensitivity of the dynamic behavior of a fast breeder reactor to large changes in delayed neutron energies following postulated reactivity accidents. The positive ramp rates are introduced not to simulate physical possibilities but solely to test the sensitivity to delayed neutron spectral changes under different conditions. A limited number of transient calculations are made using the point-kinetics code SENSTVTY, six precursor groups, and Doppler feedback. The calculational method and the reactor model are described. Delayed neutron requirements in reactor dynamics are discussed, and a brief review of the sensitivity studies is presented. The results of the sensitivity calculations indicate that the relative power, the peak power, and the accident energy release are sensitive to changes in βeff resulting from uncertainty in the delayed spectral data, but the sensitivity of the relative power is much greater than the peak power and the accident energy release. The spread in the maximum reactivity reached is found to be ∼18%, and the time spread in the melting of fuel and cladding is in milliseconds.