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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Mar 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
April 2025
Nuclear Technology
Fusion Science and Technology
Latest News
In an international industry, regulators cross the border too
Since nuclear physics works the same in Ontario as it does in Tennessee, the industry has been trying to create a reactor that can be deployed on both sides of the border. Now, the Nuclear Regulatory Commission and the Canadian Nuclear Safety Commission have decided that some of their rulings can cross the border too.
Technical Session|Sponsored by RPSD
Thursday, December 2, 2021|10:00–11:45AM EST |Columbia 1
Session Chair:
Fatma Abdelrahman
Alternate Chair:
Jeffrey A. Favorite
Session Organizer:
Amir A. Bahadori
Student Assistant:
Mitchell Mika
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Calculating the Differential Physics of Neutron Transport in Oxygen Based on Integral Experiments from the Livermore Pulsed Sphere Program
10:05–10:25AM EST
L. M. Rolison (LANL), M. L. Fensin (LANL), K. C. Kelley (LANL), S.S. McCready (LANL)
Paper
Investigation of a Portable Active Neutron Interrogation System Using MCNP
10:25–10:45AM EST
Sanchit Sharma (Kansas State Univ.), Diego Laramore (Kansas State Univ.), William L. Dunn (Kansas State Univ.), Walter J. McNeil (Kansas State Univ.), Amir A. Bahadori (Kansas State Univ.)
Impact of Fission Spectrum Modeling on Aging Estimations of Pressurized Water Reactor Vessels
10:45–11:05AM EST
Romain Vuiart (IRSN), Patrizio Console Camprini (ENEA), Kenneth W. Burn (ENEA), Mariya Brovchenko (IRSN), Julien Taforeau (IRSN), Eric Dumonteil (CEA)
Sensitivity of Pressurized Water Reactors Vessels Aging to Fuel Composition
11:05–11:25AM EST
Benjamin Benedet (IRSN), Romain Vuiart (IRSN), Julien Taforeau (IRSN), Mariya Brovchenko (IRSN)
A (Meta-)Model Driven Approach to MCNP Modeling and Editor Services
11:25–11:45AM EST
Peter J. Kowal (Rensselaer Polytechnic Institute), Jonathan A. Eugenio (Rensselaer Polytechnic Institute), Kurt A. Dominesey (Rensselaer Polytechnic Institute), Camden E. Blake (Rensselaer Polytechnic Institute), Robert A. Lefebvre (ORNL), Forrest B. Brown (Univ. of New Mexico), Wei Ji (Rensselaer Polytechnic Institute)
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