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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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
Brian Kelleher, Kieran Dolan, Mark Anderson, Kumar Sridharan
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 239-252
Technical Paper | doi.org/10.13182/NT15-140
Articles are hosted by Taylor and Francis Online.
A compact electrochemical probe has been used to measure the redox potential ranges of molten Li2BeF4, a candidate nuclear reactor coolant commonly referred to as flibe, via a dynamic beryllium reference electrode. This probe is capable of operating on a loop, but was used on a static system in salt at temperatures up to 600°C. The probe has been used to measure Li2BeF4 salt with observed redox potentials ranging from −1.792 ± 0.002 V to −0.465 ± 0.134 V, yielding individual errors as low as ± 4 mV, and weighted groupings with errors as low as ± 1 mV. The most reducing measurement taken with acceptable error was −0.962 ± 0.011 V. This probe can be adapted for use in many laboratory experiments using flibe and should be considered for any corrosion experiment supporting the development of a next-generation molten salt reactor.