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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
May 2025
Fusion Science and Technology
Latest News
Two updated standards on criticality safety published
The American National Standards Institute (ANSI) recently approved two new American Nuclear Society standards covering different aspects of nuclear criticality safety (NCS).
Technical Session
Thursday, May 19, 2022|8:00–9:45AM EDT|Brighton III/IV
Session Chair:
Carlo Fiorina (EPFL)
Track Organizer:
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Recent Developments in the OpenMC Monte Carlo Particle Transport Code
Paul K. Romano (ANL), Patrick C. Shriwise (ANL), Sterling M. Harper (TerraPower), Andrew E. Johnson (Ultra Safe Nuclear Corp.), Amanda L. Lund (ANL), Jingang Liang (Tsinghua Univ.), John R. Tramm (ANL), Andrew Davis (Culham Centre for Fusion Energy), Daniel Short (Culham Centre for Fusion Energy), Younghui Park (Univ. Wisconsin, Madison)
Paper
Automatic Conversion of MCNP Geometries to TRIPOLI-4®
Davide Mancusi (CEA)
Verification of OpenMC Neutronic Code for Transuranic Waste Incineration in Reduced Moderation Boiling Water Reactor
Sivakorn Sansawas (King Mongkut's Univ. Technology Thonburi), Saksorn Ruangtanusak (King Mongkut's Univ. Technology Thonburi), Yanin Sukjai (King Mongkut's Univ. Technology Thonburi)
Pre-Release Validation Database for the Multi-Dimensional Fuel Performance Code OFFBEAT
A. Scolaro (École Polytechnique Fédérale de Lausanne), C. Fiorina (École Polytechnique Fédérale de Lausanne), I. Clifford (Paul Scherrer Institute), E. Brunetto (École Polytechnique Fédérale de Lausanne), A. Pautz (Paul Scherrer Institute)
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