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Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
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.
