ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2023 ANS Annual Meeting
June 11–14, 2023
Indianapolis, IN|Marriott Indianapolis Downtown
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 2022
Jul 2022
Latest Journal Issues
Nuclear Science and Engineering
November 2022
Nuclear Technology
December 2022
Fusion Science and Technology
Latest News
Route readiness elements in a large-scale spent nuclear fuel transportation system
The scale and duration of a national campaign to transport spent nuclear fuel (SNF) from commercial nuclear power plants around the United States would be unprecedented. A meticulous level of planning that considers many elements is needed to inspire public confidence and support.
Technical Session
Thursday, May 19, 2022|1:30–3:15PM EDT|Haselton
Session Chair:
Vince Wang (U. of Utah)
Alternate Chair:
Petri Guimaraes (Studsvik Scandpower)
Session Organizer:
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A Preliminary Design of High Dominance Ratio Configurations for Space-Time Effect Measurements in ZPR : A Tentative Application in VENUS-F
Kornilios Routsonis (NRG), Patrick Blaise (CEA), Jean Tommasi (CEA)
Summary
Impact of Infinite Lattice Approximation on Nuclear Safety Evaluation Due to Different Fuel Assembly Loading and Core Configurations
Sebastien Bonthoux (IRSN), Julien Taforeau (IRSN)
Westinghouse Simplified RAVE™ Approach to PWR OT∆T/OP∆T Event Analyses
Peter A. Hilton (Westinghouse Electric Co.), Yixing Sung (Westinghouse Electric Co.), Bedirhan Akdeniz (Westinghouse Electric Co.), Scott Snider (Westinghouse Electric Co.), David A. Salazar (Westinghouse Electric Co.), Michael Gavalek (Westinghouse Electric Co.)
On the Modelling of Fuel Assembly Vibrations Using Coarse Mesh Approaches
C. Demaziere (Chalmers Univ. of Technology)
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