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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
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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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Goodluck I. Ofoegbu, Scott Painter, Rui Chen, Randall W. Fedors, David A. Ferrill
Nuclear Technology | Volume 134 | Number 3 | June 2001 | Pages 241-262
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT01-A3199
Articles are hosted by Taylor and Francis Online.
The percolation flux through the unsaturated zone at the proposed Yucca Mountain repository for high-level nuclear waste can potentially affect (a) the occurrence and magnitude of water influx into the emplacement drifts, (b) the onset and rates of waste-package corrosion, (c) the mobilization of waste into aqueous states, and (d) the transport of radionuclides to the saturated zone. The magnitude and spatial and temporal variations of percolation flux depend on the infiltration rate but may be significantly influenced by (a) lateral diversion of flow at stratigraphic interfaces between nonwelded and welded tuffs above the repository horizon, (b) focusing of flow within or near steeply dipping fault zones, and (c) lateral diversion of flow within thermal-mechanical altered zones. Results from numerical modeling are presented to argue that (a) areas of the repository located close to and on the up-dip side of faults that intersect the Paintbrush nonwelded Tuff (PTn) would experience elevated percolation flux, irrespective of whether the faults act as flow barriers or conduits; (b) mechanical response of the rock mass to waste-generated heat will likely cause the development of laterally discontinuous zones characterized by dilation of horizontal fractures and net dilation or closure of vertical fractures; (c) areas of the repository located on the downstream side of the thermal-mechanical altered zones would experience elevated percolation flux; and (d) repository areas subjected to elevated percolation flux would experience faster rewetting of dryout zones and, thus, longer periods of wetness and elevated humidity. These results indicate that models used to predict the occurrence and magnitudes of water influx into emplacement drifts and the variations of relative humidity within the drifts need to consider the location of the drifts relative to faults that intersect the PTn and the development, geometry, and hydrological characteristics of thermal-mechanical altered zones.