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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.”
Anthony L. Crawford (INL), David Estrada, Kiyo Fujimoto (Boise State Univ)
Proceedings | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technolgies (NPIC&HMIT 2019) | Orlando, FL, February 9-14, 2019 | Pages 1530-1537
This paper presents a test platform capable of applying representative in-pile thermal and monotonic, cyclic, and dynamic force loadings which induce target strain into representative in-pile components. The system’s form is that of two concentric linear delta robots and an intermediate vertical furnace. The enabled relative motion between the end effector platforms will result in enhanced performance compared to single delta or nearly any other Cartesian translational system by doubling the speed, quadrupling the workspace, and being able to actively prevent vibrational damage to its mechanical components. The employed force/torque sensors and motors are sized to apply/measure the target ranges, sensitivities, and bandwidths representative of in-pile loadings for objects of interest. The system has been designed to accommodate many in-pile geometries including a conventional (15mm OD x 12mm ID) fuel pin. Collet chucks attached to the force/torque sensors are designed to secure the pin ends as it transgresses through a furnace tube cavity allowing it to be thermally and/or force loaded. Such a configuration allows material characterization and sensor qualification/development to be performed. The system’s current configuration will have the ability to execute a comprehensive thermal and force loaded strain gauge study. Considered strain gauges in this future study will include conventional resistive strain gauges, weldable resistive strain gauges, and printed capacitive based strain gauges. The printed capacitive strain gauges being developed by this effort are of highest interest due to preliminary results indicating that their performance measures are more compatible with in-pile environments than their commercial counterparts. The test platform will be a critical element in validating the performance of the employed nuclear grade inks for aerosol jet printing, the printing and physical characterization of the printed structures, and the evaluation of sensor performance pre and post-irradiation.