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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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ANS standard updated for determining meteorological information at nuclear facilities
Following approval in October from the American National Standards Institute, ANSI/ANS-3.11-2024, Determining Meteorological Information at Nuclear Facilities, was published in late November. This standard provides criteria for gathering, assembling, processing, storing, and disseminating meteorological information at commercial nuclear power plants, U.S. Department of Energy/National Nuclear Security Administration nuclear facilities, and other national or international nuclear facilities.
T. V. Dury, M. T. Dhotre
Nuclear Science and Engineering | Volume 165 | Number 1 | May 2010 | Pages 101-116
Technical Paper | doi.org/10.13182/NSE08-90
Articles are hosted by Taylor and Francis Online.
Current designs of pressurized water reactors (PWRs) employ a boric acid solution in the primary cooling water to control core reactivity during operation and shutdown. However, situations could theoretically occur in which diluted borated water is present in the primary circuit. Scale experiments have been performed for a single-pump start-up, with subsequent computational fluid dynamics (CFD) simulation, to examine the accuracy with which the concentration distribution of diluted borated water entering a reactor core can be predicted. It was concluded that higher-order advection schemes must be used to obtain sufficient resolution of the velocity field and capture the larger-scale effects of the flow but that each turbulence model produces a different core-inlet boron concentration development and distribution. Though it was not the most sophisticated available, the two-equation RNG k- turbulence model produced the closest agreement with experiment. However, mesh independence of the computational results was not achieved. As a sequel to this scaled CFD study, a simulation was carried out of a full-size three-loop Siemens-type PWR featuring a perforated cylindrical flow baffle in the lower plenum. Results again showed different characteristics in time and space, depending on the turbulence model used. Comparative assessment of the results obtained with the code CFX-5 showed that correct geometrical modeling of a perforated flow baffle in the lower plenum is essential, as a porous medium representation of the baffle can lead to serious underprediction of mixing. This occurred particularly with the RNG model but also using more sophisticated turbulence models. Further refinement of the mesh is now necessary to achieve mesh independence of the results. This requires access to a massively parallel computer system.