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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!
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Nuclear News 40 Under 40 discuss the future of nuclear
Seven members of the inaugural Nuclear News 40 Under 40 came together on March 4 to discuss the current state of nuclear energy and what the future might hold for science, industry, and the public in terms of nuclear development.
To hear more insights from this talented group of young professionals, watch the “40 Under 40 Roundtable: Perspectives from Nuclear’s Rising Stars” on the ANS website.
George M. Jacobsen, Hangbok Choi, James A. Turso, Amanda M. Johnsen, Andrew J. Bascom, Xialu Wei, Eugene A. Olevsky
Nuclear Technology | Volume 208 | Number 1 | January 2022 | Pages 27-36
Technical Paper | doi.org/10.1080/00295450.2021.1877504
Articles are hosted by Taylor and Francis Online.
Zirconium silicide (Zr3Si2) is a heavy reflector material particularly effective for application to a Gas-cooled Fast Reactor (GFR) such as the General Atomics Energy Multiplier Module (EM2) and Fast Modular Reactor (FMR). In this work, the manufacturability of a high-density Zr3Si2 compound, in the Zr3Si2 phase, was investigated using hot-pressing and spark-plasma-sintering methods. The microstructure, composition, and thermal properties of the resulting hot-pressed material were measured, resulting in a 96% relative density and a 96% phase pure material. The thermal properties were consistent with those necessary for use under GFR operating conditions. The structural and dimensional stability of the material was also measured before and after neutron irradiation up to 1017 n/cm2 in the research reactor, resulting in an average linear dimensional change of <0.12%. The preliminary irradiation tests also confirmed the micromechanical stability of the Zr3Si2 phase, with no evidence of microcracking after irradiation. The results of the irradiation tests verify the fabrication method of Zr3Si2 for nuclear applications, but further irradiation tests under high-temperature and high-irradiation conditions will be required to qualify the material for GFR applications.