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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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!
Latest Magazine Issues
Nov 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Japanese researchers test detection devices at West Valley
Two research scientists from Japan’s Kyoto University and Kochi University of Technology visited the West Valley Demonstration Project in western New York state earlier this fall to test their novel radiation detectors, the Department of Energy’s Office of Environmental Management announced on November 19.
Technical Session
Wednesday, May 18, 2022|3:30–5:15PM EDT|Brighton III/IV
Session Chair:
Raphaelle Ichou
Alternate Chair:
Mark D. DeHart
Session Organizer:
John D. Bess
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Calculation Methods of B4C Control Rod Curves in a Fast VENUS-F Reactor
N. Messaoudi (SCK CEN), A. Kochetkov (SCK CEN), A. Krasa (SCK CEN), G. Vittiglio (SCK CEN), J. Wagemans (SCK CEN), G. Van den Eynde (SCK CEN), M. Sarotto (ENEA), V. Fabrizio (ENEA)
Paper
Millimetric Fuel Rod Displacements: An Experimental Study of the Impact on Local Thermal Neutron Flux in the CROCUS Reactor
F. Vitullo (École Polytechnique Fédérale de Lausanne), V. Lamirand (École Polytechnique Fédérale de Lausanne), T. Ligonnet (École Polytechnique Fédérale de Lausanne), O. Pakari (École Polytechnique Fédérale de Lausanne), D. Godat (École Polytechnique Fédérale de Lausanne), P. Frajtag (École Polytechnique Fédérale de Lausanne), A. Pautz (École Polytechnique Fédérale de Lausanne)
Research and Preliminary Application of the Improved Multicell Method for the PWR Fuel Assemblies Adjacent to the Baffle Reflector
Chenghui Wan (Xi’an Jiaotong Univ.), Wenchang Dong (Xi’an Jiaotong Univ.), Wei Shen (CANDU Owner Group), Hongchun Wu (Xi’an Jiaotong Univ.)
Nuclear Data Uncertainty Quantification for the Nuclide Inventory of a Calvert Cliffs Spent Fuel Sample
F. Grimaldi (SCK CEN), L. Fiorito (SCK CEN), P. Romojaro (SCK CEN), A. Hernandez-Solis (SCK CEN)
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