ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Feb 2026
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
February 2026
Nuclear Technology
January 2026
Fusion Science and Technology
Latest News
LLNL offers tools to model the economics of inertial fusion power plants
Lawrence Livermore National Laboratory has designed a model to help assess the economic impact of future fusion power plant operations—specifically, the operation of inertial fusion energy (IFE) power plants. Further, it has made its Generalized Economics Model (GEM) for Fusion Technology—an Excel spreadsheet—available for download.
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
To access paper attachments, you must be logged in and registered for the meeting.
Register NowLog In
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)
To join the conversation, you must be logged in and registered for the meeting.