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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
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
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.”
Gregory Mathieu, Amélie de Hoyos, (Inst de Radioprotection et de Sûreté Nucléaire), Sitakanta Mohanty, Stuart Stothoff, Michael Muller (CNWRA)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 380-388
Simulations that combine flow modeling with radionuclide transport modeling provide insights into the performance of a hypothetical geologic repository for radioactive waste. Key parameters driving performance can be identified and quantified using probabilistic sampling of the model parameters. This paper presents a probabilistic framework, referred to as the MC-MELODIE hydrologic flow and contaminant transport model, for analyzing flow and transport behavior in the context of intermediate level long-lived (ILLLW) and high-level (HLW) disposal in a deep geological formation at the Meuse/Haute-Marne (MHM) site in France. The flow and transport framework includes nested, but separate, simulations with common parameters in order to consider small-scale features (detailed drift and shaft configurations) within the repository formation while also considering large-scale (regional) release. Specific analyses use one-million-year simulations with a conservative tracer and assuming instantaneous failures and steady flow to examine the effect of repository layout on radionuclide transfer to the surrounding aquifers through the host formation and engineered features, and to illustrate how uncertainties in far-field conditions and potential future human activities may affect the fate of released radionuclides.