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Division Spotlight
Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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February 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Ontario eyes new nuclear development
A 1,300-acre site left undeveloped on the shores of Lake Ontario four decades ago could see new life as the home to a large nuclear facility.
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%.