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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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Fusion Science and Technology
February 2024
Latest News
From South Korea to Belgium: Testing a high-density research reactor fuel
The Korea Atomic Energy Research Institute has developed a high-density uranium silicide fuel designed to replace high-enriched uranium in research reactors. Recent irradiation tests appear to be successful, KAERI reports, which means the fuel could be commercialized to continue a key global nuclear nonproliferation effort—converting research reactors to run on low-enriched uranium fuel.
I. P. Maksimkin, A. A. Yukhimchuk, I. E. Boitsov, I. L. Malkov, A. Yu Baurin, S. K. Grishechkin, E. V. Shevnin
Fusion Science and Technology | Volume 60 | Number 4 | November 2011 | Pages 1519-1522
Interaction with Materials | Proceedings of the Ninth International Conference on Tritium Science and Technology (Part 2) | doi.org/10.13182/FST11-A12721
Articles are hosted by Taylor and Francis Online.
The paper presents research results related to the impact of high-pressure hydrogen (80 MPa) and radiogenic 3He and their synergetic effect on mechanical properties and structure of CrNi40MoCuTiAl alloy within the temperature range from room temperature to 873K.The samples of three different 3He concentrations have been prepared for research: [approximately equal] 30, [approximately equal] 80 and [approximately equal] 190 appm. The buildup of 3He has been fulfilled using “tritium trick” technique.The tests at room temperature have shown the increasing conventional yield strength (0.2) and decreasing plasticity characteristics (total elongation 5 and reduction of area ) depend on 3He concentration increasing. However at 873 K test temperature the alloy with the maximum 3He ([approximately equal] 190 appm) concentration turned out to be more plastic than the alloy with 3He [approximately equal] 30 and 80 appm concentration.