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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 Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Securing the advanced reactor fleet
Physical protection accounts for a significant portion of a nuclear power plant’s operational costs. As the U.S. moves toward smaller and safer advanced reactors, similar protection strategies could prove cost prohibitive. For tomorrow’s small modular reactors and microreactors, security costs must remain appropriate to the size of the reactor for economical operation.
Do Heon Kim, Hangbok Choi, Won Sik Yang, Jong Kyung Kim
Nuclear Science and Engineering | Volume 137 | Number 1 | January 2001 | Pages 23-37
Technical Paper | doi.org/10.13182/NSE01-A2173
Articles are hosted by Taylor and Francis Online.
The effect of DUPIC fuel composition heterogeneity on CANDU core performance was assessed for three candidate DUPIC fuel options: the fissile content adjustment method, reactivity control by slightly enriched and depleted uranium, and reactivity control by natural uranium. The fissile content adjustment method produces DUPIC fuel of fixed 235U and 239Pu contents, while the reactivity control method produces DUPIC fuel of uniform reactivity at the fresh condition. To assess the uncertainty of the core performance parameter associated with the isotopic variation, the sensitivity coefficients were generated by the generalized perturbation theory for the lattice parameter and zone controller level perturbations. The uncertainty was then estimated for three key core performance parameters: maximum channel power (MCP), maximum bundle power (MBP), and channel power peaking factor (CPPF). The fissile content adjustment method was shown to have a smaller uncertainty in the core performance parameter than with the reactivity control options. For the fissile content adjustment method, the average uncertainties of MCP, MBP, and CPPF were estimated to be 1.3, 2.5, and 1.2%, respectively, with 95% confidence level, when simulated for specified burnup points of the equilibrium core.