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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Why should safeguards by design be a global effort?
Jeremy Whitlock
I can’t think of a more exciting time to be working in nuclear, with the diversity of advanced reactor development and increasing global support for nuclear in sustainable energy planning. But we can’t lose sight of the need to plan for efficient international safeguards at the same time.
Global nuclear deployment has been underpinned since 1970 by the Treaty on the Non-Proliferation of Nuclear Weapons (NPT), making it a key customer requirement for governments to demonstrate unequivocally that the technology is not being misused for weapons development.
The International Atomic Energy Agency (IAEA) has helped verify this commitment for more than 50 years, but it has never safeguarded many of the advanced reactors (and related fuel cycle processes) being developed today.
S. Gordeev, L. Stoppel, R. Stieglitz, M. Daubner, F. Fellmoser
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 301-308
Fusion Materials | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8918
Articles are hosted by Taylor and Francis Online.
The target assembly of the International Fusion Materials Irradiation Facility (IFMIF) consists of a nozzle, which has to form a stable lithium jet. Therefore, a flat uniform velocity distribution at the nozzle outlets cross-section with a simultaneously low turbulence intensity is required to ensure a safe operation. These boundary conditions necessitate a detailed knowledge on the turbulent flow in contraction nozzles in order identify turbulence models accurately predicting experimental findings within the velocity range of interest for nuclear target and hence can then act as design optimization tool.In order to validate commercially available Computational Fluid dynamic codes (CFD) and the turbulence models incorporated in them a series of experiments using water as model fluid are conducted in the Liquid-Metal-Laboratory KALLA at the research center Karlsruhe. A number of turbulence models with different extensions for the near wall treatment were tested versus the experimentally obtained data. Based on this comparison a hydraulic analysis of the contraction nozzle flow is performed taking into account the relaminarization of the accelerated flow, the occurrence of secondary motions and their impact on the development of the boundary layer. In summary the V2F turbulence model exhibits the best agreement between numerical and experimental data and thus can be considered to be most suitable for the simulation of the accelerated nozzle flow for free surface target applications.