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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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
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.
Günter Fieg, Manfred Möschke, Heinrich Werle
Nuclear Technology | Volume 99 | Number 3 | September 1992 | Pages 309-317
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34715
Articles are hosted by Taylor and Francis Online.
The potential for recriticalities and high energetics during the transition phase of a hypothetical coredisruptive accident in a liquid-metal fast breeder reactor is strongly dependent on the fissile fuel inventory remaining in the core region. To investigate the ability of the fuel to penetrate unblocked flow paths, a series of experiments with pin bundle geometry has been performed at the THEFIS facility using alumina and alumina-iron melts as fuel simulants. Several series of similar experiments were done previously with tubes, annuli, and three-pin bundles using alumina, iron, and mixtures of alumina and iron melts. In this new series, seven-pin bundles with wire wrappers and grid spacers defining the cooling channels between the single pins have been investigated. These bundles are a more realistic representation of the upper blanket structure. These out-of-pile experiments have been analyzed with the PLUGM code, which is based on the assumption of stable crust growth during the penetration and freezing process. The differences in results between out-ofpile experiments using alumina and those using UO2 are discussed, and an explanation for these discrepancies is indicated.