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
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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Jun 2024
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Nuclear Science and Engineering
August 2024
Nuclear Technology
July 2024
Fusion Science and Technology
Latest News
NRC engineers share their expertise at the University of Puerto Rico
Robert Roche-Rivera and Marcos Rolón-Acevedo are licensed professional engineers who work at the U.S. Nuclear Regulatory Commission. They are also alumni of the University of Puerto Rico–Mayagüez (UPRM) and have been sharing their knowledge and experience with students at their alma mater since last year, serving as adjunct professors in the university’s Department of Mechanical Engineering. During the 2023–2024 school year, they each taught two courses: Fundamentals of Nuclear Science and Engineering, and Nuclear Power Plant Engineering.
Y. F. Chen, Y. F. Chiou, S. J. Chang, S. H. Jiang, R. J. Sheu
Nuclear Technology | Volume 182 | Number 2 | May 2013 | Pages 224-234
Regular Technical Paper | Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Radiation Transport and Protection | doi.org/10.13182/NT13-A16432
Articles are hosted by Taylor and Francis Online.
Surface dose rate distribution over a spent nuclear fuel dry storage cask was realistically evaluated using the MONACO with Automated Variance Reduction using Importance Calculations (MAVRIC) computational sequence in the SCALE6 code system, with special emphasis on the effects of detailed modeling on the source term and cask geometry. The first storage cask in Taiwan has been fabricated and will be ready for loading of the designated spent fuels from Taiwan Power Company's first nuclear power plant. A test run is scheduled for 2013.Neutron and gamma-ray source terms of the first batch of 56 spent fuels were determined one by one according to their specifications, burnup histories, and cooling times. The geometry of the cask was modeled in detail including the prescribed loading pattern of 56 spent fuels in the canister. MAVRIC was modified to allow specification of the source intensity and the axial distribution for each fuel bundle, and this resulted in a factor of 3 difference in the calculated surface dose rates from fuel gammas. The main purpose for such comprehensive and detailed modeling was to compare the results with a simplified model and to predict a dose rate distribution as realistically as possible in preparation for making a high-quality comparison with field measurements. In addition to checking assumptions adopted in the safety analysis report, the results of this study can provide useful guidance for the preparation of a health physics program during the test run and, more importantly, pave the way for establishing a valuable benchmark problem.