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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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
Feb 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
March 2025
Nuclear Technology
February 2025
Fusion Science and Technology
Latest News
Neutron Vision at Los Alamos: Exploring the Frontiers of Nuclear Materials Science
In materials science, understanding the unseen—how materials behave internally under real-world conditions—has always been key to developing new materials and accelerating innovative technologies to market. Moreover, the tools that allow us to see into this invisible world of materials have often been game-changers. Among these, neutron imaging stands out as a uniquely powerful method for investigating the internal structure and behavior of materials without having to alter or destroy the sample. By harnessing the unique properties of neutrons, researchers can uncover the hidden behavior of materials, providing insights essential for advancing nuclear materials and technologies.
Technical Session|Sponsored by RPD
Wednesday, November 20, 2024|8:00–9:45AM EST|Canaveral 3
Session Chair:
Akio Yamamoto
Alternate Chair:
Manit D. Shah (ORNL)
Session Organizer:
Zeyun Wu (Virginia Commonwealth Univ.)
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Comparative Analysis of Heat Deposition Rates and DPA in the HFIR Flux Trap to Support LEU Conversion
8:00–8:20AM EST
K.M. Burg (ORNL), D. Hartanto (ORNL), D. Chandler (ORNL), J.W. Bae (ORNL), Y.E. Robert (ORNL)
Paper
Development Status of MCSTD-GPU: GPU-Based Monte Carlo Time-Dependent Code for Reactor Transient Analysis
8:20–8:40AM EST
Eun Jeong (Ulsan Nat'l Institute Science and Technology), Deokjung Lee (Ulsan Nat'l Institute Science and Technology)
Code-to-Code Verification of the ARC Codes on a 1500 MWth Metallic-Fueled SFR Core
8:40–9:00AM EST
Ahmed A. Abdelhameed (ANL), Kyle Ramey (ANL), Kalin Kiesling (ANL), Nicolas E. Stauff (ANL)
Flux Characterization of Washington State University's Epithermal Neutron Beam Facility
9:00–9:20AM EST
Travis J. Zipperer (PNNL), Larry R. Greenwood (PNNL), Bruce D. Pierson (PNNL), Walter G. Luscher (PNNL), Hillary L. Bennett (Washington State), Corey Hines (Washington State)
2D Cylindrical SP3 Transport Calculation Using Finite Volume Method with Cross-Diffusion Treatment for Unstructured Meshes
9:20–9:40AM EST
Tomohiro Endo (Nagoya Univ.), Akio Yamamoto (Nagoya Univ.)
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