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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
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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Nuclear Science and Engineering
June 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Bipartisan Fusion Energy Act pushes for regulatory clarity
Padilla
Sen. Alex Padilla (D., Calif.) introduced the Fusion Energy Act (S. 4151) last month with a bipartisan group of cosponsors—John Cornyn (R., Texas), Cory Booker (D., N.J.), Todd Young (R., Ind.), and Patty Murray (D., Wash.). The legislation would codify the Nuclear Regulatory Commission’s regulatory authority over commercial fusion energy systems to streamline the creation of clear federal regulations that will support the development of commercial fusion power plants—and would require a report within one year on a study of risk- and performance-based, design-specific licensing frameworks for “mass-manufactured fusion machines.
“Congress must do everything in its power to ensure continued U.S. leadership in developing commercial fusion energy facilities,” said Padilla as he introduced the bill. “The Fusion Energy Act would provide regulatory certainty for investors as the NRC develops and streamlines frameworks for such facilities.”
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.