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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
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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.”
Orlin L. Blajiev, Chihiro Matsuura, Daisuke Hiroishi, Kenkichi Ishigure
Nuclear Technology | Volume 137 | Number 1 | January 2002 | Pages 60-71
Technical Paper | Radioisotopes | doi.org/10.13182/NT02-A3257
Articles are hosted by Taylor and Francis Online.
The corrosion behavior of Zircaloy-2 in the presence of Zn was investigated. Zinc is a possible technological additive to be injected in the coolant to reduce the 60Co buildup. However, its influence on the cladding corrosion, alone or in combination with some typical corrosion impurities, as, for example, Cr, has not been considered so far. Because of this, the surface composition and electrochemical properties of Zircaloy specimens were investigated after their exposure to Zn2+, CrO42-, and CrO42- + Zn2+ aqueous solutions at 250°C. It was found that zinc-containing phases did not deposit from solutions containing on Zn2+ ions. Amorphous Cr3+-oxide and ZnCr2O4 ferrite phases were found on the surface of the samples after their exposure to CrO42- and CrO42- + Zn2+ environments, respectively. The amounts of the deposited Cr and Zn + Cr strongly depended on the times of the preconditioning of the Zircaloy specimens in high-temperature water. The rate of the oxide precipitation declined with increasing exposure time to both the CrO42- and CrO42- + Zn2+ solutions. The electrochemical measurement showed that the limiting factor of the Cr and Zn + Cr deposition reaction was the reduction of Cr(VI) to Cr(III). The reduction completely depended on the resistance of ZrO2, Cr, and Zn + Cr oxides, which increased with the time of preconditioning and exposure. A thermodynamic analysis based on oxide solubilities was applied to explain the different deposition pathways in the CrO42- and CrO42- + Zn2+ environments. In view of the decreasing deposition rate of the Zn - Cr-oxide phases, it could be concluded that their limited precipitation and presence do not have a significant adverse effect on the fuel cladding corrosion.
