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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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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.”
R. N. Nair, T. M. Krishnamoorthy
Nuclear Technology | Volume 114 | Number 2 | May 1996 | Pages 235-245
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT96-A35252
Articles are hosted by Taylor and Francis Online.
Mathematical models have been developed to predict the spatial and temporal profiles of radionuclide concentration in the near field and far field of a shallow land burial facility. The disposal facility considered is a reinforced concrete vault located 2.9 m above the water table. The source term is derived from leaching considerations based on diffusion-controlled kinetics for the transfer of radionuclides from the cylindrical waste form into the surrounding pore water of the backfill material. The concentration of radionuclides in the backfill at the bottom boundary of the vault is converted to a release rate into the near field using the outgoing water flux. The delay and decay during transit in the sand and soil layers are taken into account while evaluating the concentration and release at the near field-water table boundary. Using this release rate as the inlet flux, the concentration of radionuclides in the groundwater has been computed using a two-dimensional model. Results indicate that the vault facility with cement as the backfill material could contain almost all the radionuclides commonly encountered in the waste stream generated during the operation of nuclear power plants. However, the storage of some of the long-lived radionuclides produced in fuel reprocessing plants such as 79Se, 99Tc and 129I in the vault facility need to be regulated for restricting the resultant dose within the apportioned dose limit prescribed for the facility.