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Division Spotlight
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.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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.”
Mohamed Tahar Sissaoui, Guy Marleau, Daniel Rozon
Nuclear Technology | Volume 125 | Number 2 | February 1999 | Pages 197-212
Technical Paper | Fission Reactors | doi.org/10.13182/NT99-A2942
Articles are hosted by Taylor and Francis Online.
A new model has been developed to evaluate the variation of few-group cross sections with local parameters and the history of the reactor. This model allows us to generate a coherent set of nuclear cross sections for a CANDU cell. The history dependence of the nuclide concentrations is taken into account by creating a pseudo-isotope, which includes actinides whose concentrations are strongly affected by local parameter history. Simple physical considerations lead us to determine the law of variation of the cross sections as a function of these parameters. They permit the computation of the cross sections for each state of the reactor core, using a unique library for each type of cell, which contains the nuclear cross sections computed at nominal conditions and feedback coefficients. To validate the feedback model, several operational situations were tested, and the results are compared to those given by a transport calculation using the DRAGON cell code.