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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Eleodor Nichita
Nuclear Science and Engineering | Volume 175 | Number 2 | October 2013 | Pages 157-171
Technical Paper | doi.org/10.13182/NSE12-59
Articles are hosted by Taylor and Francis Online.
Modern analysis of nuclear reactor transients uses space-time reactor kinetics methods. In the Canadian nuclear industry, safety analysis calculations use almost exclusively the improved quasi-static (IQS) flux factorization method. The IQS method, like all methods based on flux factorization, relies on calculating effective point-kinetics parameters, which dominate the time behavior of the flux, using adjoint-weighted integrals. The accuracy of the adjoint representation influences the accuracy of the effective kinetics parameters.Routine full-core calculations are not performed using detailed models and transport theory, but rather using a cell-homogenized model and two-group diffusion theory. This work evaluates the effect of homogenization and group condensation on the calculated effective kinetics parameters of an equilibrium CANDU core.Results show that homogenization combined with group condensation introduces a positive bias of ~5% in the effective delayed neutron fraction over a wide range of discharge burnups. Homogenization alone induces a positive bias of only ~2%.The bias in the effective generation time is <1% for all studied discharge burnups, and its effect on the results of a positive-reactivity transient is found to be negligible, with differences being caused solely by the effective delayed neutron fraction bias. The fractional delayed neutron fraction bias for the equilibrium core is found to be very close to that for a fresh-fuel core. However, because of the lower effective delayed neutron fraction of the equilibrium core, the effects of the bias are larger for the equilibrium core than for the fresh-fuel core. For a sample positive-reactivity transient, the maximum power is found to be underestimated by 9% for the fresh core and by 14% for the equilibrium core as a consequence of homogenization and group condensation.