ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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Nuclear Science and Engineering
September 2024
Nuclear Technology
August 2024
Fusion Science and Technology
Latest News
Taking shape: Fusion energy ecosystems built with public-private partnerships
It’s possible to describe fusion in simple terms: heat and squeeze small atoms to get abundant clean energy. But there’s nothing simple about getting fusion ready for the grid.
Private developers, national lab and university researchers, suppliers, and end users working toward that goal are developing a range of complex technologies to reach fusion temperatures and pressures, confounded by science and technology gaps linked to plasma behavior; materials, diagnostics, and electronics for extreme environments; fuel cycle sustainability; and economics.
M. T. Farmer, C. Gerardi, N. Bremer, S. Basu
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 461-474
Technical Paper | doi.org/10.13182/NT16-43
Articles are hosted by Taylor and Francis Online.
The reactor accidents at Fukushima Daiichi have rekindled interest in late-phase severe accident behavior involving reactor pressure vessel breach and discharge of molten core melt into the containment. Two technical issues of interest in this area are core-concrete interaction and the extent to which the core debris may be quenched and rendered coolable by top flooding. The Organisation for Economic Co-operation and Development–sponsored Melt Coolability and Concrete Interaction programs at Argonne National Laboratory included the conduct of large-scale reactor material experiments and associated analysis with the objectives of resolving the ex-vessel debris coolability issue and addressing remaining uncertainties related to long-term two-dimensional molten core–concrete interactions under both wet and dry cavity conditions. These tests provided a broad database to support accident management planning as well as the development and validation of models and codes that can be used to extrapolate the experimental results to plant conditions. This paper provides a high-level overview of the key experimental results obtained during the program. A discussion is also provided of the technical gaps that remain in this area, several of which have arisen based on the sequence of events and operator actions during Fukushima.