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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
Canada clears Darlington to produce Lu-177 and Y-90
The Canadian Nuclear Safety Commission has amended Ontario Power Generation’s power reactor operating license for Darlington nuclear power plant to authorize the production of the medical radioisotopes lutetium-177 and yttrium-90.
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.