ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Nuclear Science and Engineering
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Nuclear Technology
Fusion Science and Technology
Latest News
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.
N. P. Bhat, Hans U. Borgstedt
Fusion Science and Technology | Volume 21 | Number 1 | January 1992 | Pages 52-59
Technical Paper | Blanket Engineering | doi.org/10.13182/FST92-A29705
Articles are hosted by Taylor and Francis Online.
Electrochemical oxygen meters with yttrium-doped thoria, yttrium-stabilized zirconia, and calcium-stabilized zirconia solid electrolytes are tested for the measurement of oxygen activity in Pb-17Li eutectic alloy, the proposed breeder blanket fluid for fusion reactors. The oxygen potentials of the alloy measured by these three meters are compared with the oxygen potentials of the alloy after the addition of lithium oxide and with theoretical values. Zirconium and yttrium metal foils are tested for gettering oxygen from the alloy. The compatibility of the three ceramic materials in the liquid alloy and the stability of the meters for prolonged use are discussed. The influence of oxygen on the corrosion of steels in Pb-17Li is reviewed in light of the oxygen potentials of the alloy compared to thermodynamic data of the ternary oxides of the metal constituents of steels. The possibility of using the oxygen meters to measure the lithium activity of the alloy is also indicated.
