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Conference 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!
Latest Magazine Issues
Sep 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
Fusion Science and Technology
August 2025
Latest News
Deep Fission raises $30M in financing
Since the Department of Energy kicked off a 10-company race with its Nuclear Reactor Pilot Program to bring test reactors on line by July 4, 2026, the industry has been waiting for new headlines proclaiming progress. Aalo Atomics broke ahead of the pack first by announcing last week that it had broken ground on its 50-MWe Aalo-X at Idaho National Laboratory.
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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