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
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
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
August 2024
Nuclear Technology
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Latest News
Oklo completes end-to-end demonstration of advanced fuel recycling
Oklo Inc. has announced that it has completed the first end-to-end demonstration of its advanced fuel recycling process as part of an ongoing $5 million project in collaboration with Argonne and Idaho National Laboratories. Oklo’s goal: scaling up its fuel recycling capabilities to deploy a commercial-scale recycling facility that would increase advanced reactor fuel supplies and enhance fuel cost effectiveness for its planned sodium fast reactors.
Sylvie Aubry, Christian Caremoli, Jean Olive, Paul Rascle
Nuclear Technology | Volume 112 | Number 3 | December 1995 | Pages 331-345
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35159
Articles are hosted by Taylor and Francis Online.
Pressurized water reactor (PWR) or liquid-metal fast breeder reactor cores or fuel assemblies, PWR steam generators, condensers, and tubular heat exchangers are basic components of a nuclear power plant that involve two-phase flows in tube or rod bundles. A deep knowledge of the detailed flow patterns on the shell side is necessary to evaluate departure from nucleate boiling (DNB) margins in reactor cores, singularity effects (grids, wire spacers, support plates, and baffles), corrosion on the steam generator tube sheet, bypass effects, and vibration risks. For that purpose, Electricité de France has developed since 1986 a general purpose Thermal-HYdraulic Code (THYC) to study three-dimensional single- and two-phase flows in rod or tube bundles (PWR cores, steam generators, condensers, and heat exchangers). It considers the three-dimensional domain to contain two kinds of components: fluid and solids. The THYC model is obtained by space-time averaging of the instantaneous equations (mass, momentum, and energy) of each phase over control volumes including fluid and solids. The physical model of THYC is validated under several French and international experiments for single- and two-phase flows. The THYC is used for the calculation of transients such as steam-line break (coupled with a three-dimensional neutronics code), for DNB predictions, and for various steam generator or condenser studies.