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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
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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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Deep Isolation validates its disposal canister for TRISO spent fuel
Nuclear waste disposal technology company Deep Isolation announced it has successfully completed Project PUCK, a government-funded initiative to demonstrate the feasibility and potential commercial readiness of its Universal Canister System (UCS) to manage TRISO spent nuclear fuel.
H. J. Ahn, T. J. Kim, S. B. Park, M. H. Baik, Y. K. Choi, J. M. Park, B. K. Lee
Fusion Science and Technology | Volume 76 | Number 4 | May 2020 | Pages 596-599
Technical Paper | doi.org/10.1080/15361055.2020.1729296
Articles are hosted by Taylor and Francis Online.
Korea Hydro & Nuclear Power Company, Ltd., has operated the Wolsong Tritium Removal Facility (WTRF) since 2007 to reduce tritium concentrations in the moderator and coolant of the Wolsong nuclear power plant. As a result of the WTRF operation, the concentration of tritium in the moderator and coolant significantly decreased from 2320 to 9.3 GBq/kg. In particular, the tritium concentrations of the radioactive waste directly affected by radioactivity in the moderator and coolant were reduced by up to 99% during the WTRF operation. For this purpose, a chemical separation and quantification method for tritium separation was developed, and its average recovery yield was 98%.
