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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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.”
Bernhard Kienzler, Peter Vejmelka, Horst-Jürgen Herbert, Herbert Meyer, Corinna Altenhein-Haese
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 101-118
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3049
Articles are hosted by Taylor and Francis Online.
Experimental findings of full-scale leach tests performed on simulated cemented waste forms and self-shielded concrete waste containers for periods up to 19 yr in saturated salt brines (NaCl- and Q-brine) are presented. Measurements cover the evolution of leachant composition and the release of radionuclides such as Cs, U, and Np. Performance of the waste forms and the self-shielded concrete waste containers depends on the pore volume of the hardened cement/concrete, which is correlated to the water/cement ratio of the waste forms. Cesium release follows a linear time dependence. Samples, especially those having a high pore volume, show almost complete release of Cs in the period of investigation. Uranium release is independent of the leach period. Uranium concentrations are controlled by thermodynamic equilibrium. Neptunium is released only to a small extent; concentrations are close to the detection limit.Modeling of the cement corrosion progress allows the prediction of the evolution of the brines in terms of pH, calcium concentration, etc. and the identification of solids controlling the solubilities of the main components and of uranium.