ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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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Nuclear Science and Engineering
July 2025
Nuclear Technology
Fusion Science and Technology
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.
J. F. L. M. Brukx, G. P. R. Hansen, P. Voj
Nuclear Technology | Volume 33 | Number 1 | April 1977 | Pages 5-16
Technical Paper | Reactor | doi.org/10.13182/NT77-A31759
Articles are hosted by Taylor and Francis Online.
As part of the emergency core cooling studies for the SNR-300 reactor, the transient thermohydraulic behavior of the reactor inlet plenum was investigated. Using a simplified and scaled-down model of the plenum and using sodium as the working fluid, thermal shock experiments were performed for different mass flow rates and initial temperature differences. The measured temperature distributions of the test section were compared with calculated results of a computer program. Satisfactory agreement between theoretical and experimental results was obtained only if the influence of superimposed free convection on forced convection heat transfer was taken into account. The heat transfer coefficients used were theoretical results calculated by the computer program CØFFCØ. The experimental results consolidated the theoretical heat transfer coefficients for turbulent combined free and forced convection for a modified Rayleigh number ranging from 4 × 105 to 6 × 106.
