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
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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Latest News
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.
Akio Yamamoto, Masahiro Tatsumi, Naoki Sugimura
Nuclear Science and Engineering | Volume 163 | Number 2 | October 2009 | Pages 144-151
Technical Paper | doi.org/10.13182/NSE08-80
Articles are hosted by Taylor and Francis Online.
A new burnup calculation method, called the projected predictor-corrector (PPC) method, is proposed. In comparison with the conventional predictor-corrector (PC) method, a larger time-step size can be used in burnup calculation without losing calculational accuracy. The PPC method is especially useful for Gd-bearing fuel assemblies, for which a fine time step size is necessary in burnup calculations. The PPC method utilizes a correlation between the number density and the reaction rate in each burnable nuclide and improves the accuracy of the microscopic reaction rate in the corrector step by estimating the “projected” reaction rate. The additional computation time for the PPC method is negligible. Verification calculations are performed for 17 × 17 pressurized water reactor fuel assemblies with 16 Gd-bearing fuel rods. The content of Gd in Gd-bearing fuel rods is set to be 2 to 10 wt%. The calculation results indicate that the PPC method shows comparable accuracy to conventional PC methods whose step time size is about half; i.e., the number of burnup steps in the PPC method can be reduced to about half of that in the conventional PC method.