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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
David E. Holcomb (ORNL), Roger A. Kisner (ORNL (retired)), K. Kyle Reed, James Bate, James R. Keiser (ORNL)
Proceedings | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technolgies (NPIC&HMIT 2019) | Orlando, FL, February 9-14, 2019 | Pages 222-237
A novel in-situ corrosion sensor for structural alloys exposed to molten salts has been initially demonstrated. The measurement is based upon observing the change in magnetic susceptibility of salt wetted structural alloys as corrosion occurs. In halide salts corrosion of structural alloys proceeds primarily through dissolution of the least noble component of the alloy into the melt. All currently available structural alloys intended for use with molten salt reactors (MSRs) include nickel, chromium, and iron. Chromium is preferentially oxidized from the alloy surface by exposure to halide salts at high temperature. Diffusion within the alloy results in progressively deeper depletion of chromium from the alloy surface. Relevant chromium bearing structural alloys are paramagnetic. However, once the chromium has been depleted, they become ferromagnetic. Thus, structural alloy corrosion in an MSR results in development of a ferromagnetic surface layer whose depth increases with increasing corrosion. The corrosion sensor functions by employing the progressive increase in ferromagnetism as a transduction mechanism through including the corroding alloy in a magnetic circuit. To date we have characterized the sensor response of structural alloy samples with varying degrees of corrosion at room temperature. Over the next year, we plan to demonstrate sensor performance at MSR operating temperatures (up to 750 °C) in a piping geometry. Development of the sensor remains a work in progress as the aim is to install a corrosion monitor to operate over extended periods with only the corroding component exposed to salt (which could be the pipe itself). This configuration can be accomplished so that measurement magnetics and electronics are external to the pipe. Presumably, the instrument would continuously relay corrosion progress via electronic communications.