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Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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 2025
Nuclear Technology
Fusion Science and Technology
July 2025
Latest News
The U.S. Million Person Study of Low-Dose-Rate Health Effects
There is a critical knowledge gap regarding the health consequences of exposure to radiation received gradually over time. While there is a plethora of studies on the risks of adverse outcomes from both acute and high-dose exposures, including the landmark study of atomic bomb survivors, these are not characteristic of the chronic exposure to low-dose radiation encountered in occupational and public settings. In addition, smaller cohorts have limited numbers leading to reduced statistical power.
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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