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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.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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!
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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Dong-Seong Sohn, Gordon E. Kohse, David M. Parks, Otto K. Harling
Nuclear Technology | Volume 92 | Number 3 | December 1990 | Pages 383-388
Technical Paper | Material | doi.org/10.13182/NT90-A16239
Articles are hosted by Taylor and Francis Online.
Considerable effort is currently being expended to develop mechanical property tests for various miniature specimens. Bend tests of thin 3-mm-diam disks (standard transmission electron microscopy specimens) have been used by various workers. A miniaturized disk bend test (MDBT) using a 3-mm-diam x 0.25-mm-thick disk is described and recent progress in extracting uniaxial yield stress values from bend test data is discussed. The method is based on the existence of an initial linear region in the load/deflection curve generated by the bend test. A strong relationship between the load at deviation from linearity and the uniaxial yield stress is found. By simulating observed load/deflection curves using a finite element stress/strain analysis, yield stresses can be calculated from MDBT data. Results using our approach to MDBT for a range of materials are presented, and good agreement with uniaxial tensile test data is shown. These results for the small specimen volume required for MDBT offer interesting possibilities for monitoring the mechanical properties of in-service structures, as well as for minimizing test volumes and specimen radioactivities in such programs as alloy development for irradiation performance in fusion reactors.