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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
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
ARG-US Remote Monitoring Systems: Use Cases and Applications in Nuclear Facilities and During Transportation
As highlighted in the Spring 2024 issue of Radwaste Solutions, researchers at the Department of Energy’s Argonne National Laboratory are developing and deploying ARG-US—meaning “Watchful Guardian”—remote monitoring systems technologies to enhance the safety, security, and safeguards (3S) of packages of nuclear and other radioactive material during storage, transportation, and disposal.
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.