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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.
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2025 ANS Annual Conference
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Chicago, IL|Chicago Marriott Downtown
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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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Latest News
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.
C. A. Ordonez, R. Carrera, W. D. Booth, M. E. Oakes
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1740-1744
Impurity Control and Plasma-Facing Component | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29593
Articles are hosted by Taylor and Francis Online.
Tritium retention at the wall is an important consideration for the operation of a fusion ignition experiment. In this paper, the fusion ignition experiment IGNITEX is considered and tritium implantation, retention, and removal from the first wall are investigated. For the analysis, a new implantation model is used. The implantation model incorporates analytical fits to detailed Monte Carlo calculations of the implantation profile. The Monte Carlo calculations include the effect of the surface floating potential on the ion distribution function at the plasma-surface interface. Tritium retention at the first wall is shown to increase with incident fluence until saturation occurs. The isotope-exchange process for use in tritium removal at the wall is studied.
