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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2022)
August 7–10, 2022
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!
Latest Magazine Issues
Jun 2022
Jan 2022
Latest Journal Issues
Nuclear Science and Engineering
July 2022
Nuclear Technology
Fusion Science and Technology
Latest News
Carbon value: Lifetime extensions of nuclear reactors could save billions in climate mitigation costs
On the road to achieving net-zero by midcentury, low- or no-carbon energy sources that slash carbon dioxide emissions are critical weapons. Nevertheless, the role of nuclear energy—the single largest source of carbon-free electricity—remains uncertain.
Nuclear energy, which provides 20 percent of the electricity in the United States, has been a constant, reliable, carbon-free source for nearly 50 years. But our fleet of nuclear reactors is aging, with more than half of the 92 operating reactors across 29 states at or over 40 years old—the length of the original operating licenses issued to the power plants. While some reactors have been retired prematurely, there are two options for those that remain: retire them or renew their license.
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)
Summary
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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