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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
Latest News
Discovering, Making, and Testing New Materials: SRNL’s Center For Hierarchical Waste Form Materials
Savannah River National Laboratory researchers are building on the laboratory’s legacy of using cutting-edge science to effectively immobilize nuclear waste in innovative ways. As part of the Center for Hierarchical Waste Form Materials, SRNL is leveraging its depth of experience in radiological waste management to explore new frontiers in the industry.
Makoto Oyaidzu, Kanetsugu Isobe, Takumi Hayashi, Toshihiko Yamanishi
Fusion Science and Technology | Volume 60 | Number 4 | November 2011 | Pages 1515-1518
Interaction with Materials | Proceedings of the Ninth International Conference on Tritium Science and Technology (Part 2) | doi.org/10.13182/FST11-A12720
Articles are hosted by Taylor and Francis Online.
The effects of tritiated water on the corrosion behavior of SUS304 stainless steel was studied using Tafel extrapolation method, one of electrochemical techniques with changing tritium concentration, dissolved oxygen concentration and pH in electrolyte as parameters. It was indicated that there would be two or more effects of tritium that enhance the corrosion of SUS304 stainless steel under several experimental conditions. One is passivation inhibitory effect, which could be observed only in highly corrosive circumstance of 1N H2SO4 electrolyte. The other effects of tritium on corrosion behavior could be observed not only in 1N H2SO4 but also incorrosive circumstance of 1N Na2SO4 electrolyte, which would be affected by dissolved oxygen concentration as well as tritium concentration.