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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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!
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Nuclear Science and Engineering
February 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Fermilab center renamed after late particle physicist Helen Edwards
Fermi National Accelerator Laboratory’s Integrated Engineering Research Center, which officially opened in January 2024, is now known as the Helen Edwards Engineering Center. The name was changed to honor the late particle physicist who led the design, construction, commissioning, and operation of the lab’s Tevatron accelerator and was part of the Water Resources Development Act signed by President Biden in December 2024, according to a Fermilab press release.
Carlos E. Velasquez, Graiciany P. Barros, Claubia Pereira, Maria Auxiliadora F. Veloso, Antonella L. Costa
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 625-629
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-949
Articles are hosted by Taylor and Francis Online.
Different first wall material proposals based on tungsten alloy WNiFe, WLa2O3, W1.1TiC, W26Re, beryllium alloy S-B65, stainless steel SS316 and graphite have been studied in the last years. These materials must be capable of withstanding high temperature and neutron flux. Nevertheless, using hybrid systems, the first wall material choice could influence the criticality system due to the different properties of each material. To analyze this influence, two hybrid reactors were evaluated. The first one is a Tokamak based on magnetic confinement and the second one based on inertial confinement. Both systems contain a transmutation layer with reprocessed fuel spiked with thorium. The results showed the principal nuclides affected in the transmutation layer and the differences in the criticality due to neutron flux variations produced by the changes in the first wall material.