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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.
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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Latest News
BREAKING NEWS: Trump issues executive orders to overhaul nuclear industry
The Trump administration issued four executive orders today aimed at boosting domestic nuclear deployment ahead of significant growth in projected energy demand in the coming decades.
During a live signing in the Oval Office, President Donald Trump called nuclear “a hot industry,” adding, “It’s a brilliant industry. [But] you’ve got to do it right. It’s become very safe and environmental.”
Geoffrey R. Bull, Jason O. Oakley, Michael L. Corradini
Nuclear Science and Engineering | Volume 193 | Number 3 | March 2019 | Pages 299-313
Technical Paper | doi.org/10.1080/00295639.2018.1514195
Articles are hosted by Taylor and Francis Online.
The fissioning of uranium in an aqueous solution creates 99Mo, the precursor to 99mTc, but also generates large amounts of hydrogen and oxygen from the radiolysis of the water. When the dissolved gases reach a critical concentration, bubbles will form in the solution, affecting both the fission power and the heat transfer out of the solution. Magnesium sulfate (MgSO4) was chosen as a surrogate for uranium sulfate salt in an aqueous solution for the experiments. A high aspect ratio tank was constructed to measure heat transfer from the solution with internal gas and heat generation. A fritted glass air injection manifold allowed the exploration of bubble characteristics and flow patterns on heat transfer from the heated pool to the cold walls. Experimental data analysis provided heat transfer coefficient values as a function of axial position, power density, and the superficial gas velocity in the pool. Results, including a recommended correlation for average heat transfer coefficients, are provided for superficial gas velocities between 0 and 0.3 cm/s and power densities of 200 and 400 W/L in pH 7 and pH 1 MgSO4 solutions.