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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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Nuclear Technology
Fusion Science and Technology
Latest News
Surplus plutonium for power reactor fuel: What’s on offer
The Department of Energy has a plan for private companies to “dispose of surplus plutonium”—about 19.7 metric tons in both oxide and metal forms—by “making the materials available for advanced nuclear technologies.” A Surplus Plutonium Utilization Program request for applications (RFA) issued October 21 describes the plutonium on offer, and the “thresholds” prospective applicants must meet.
C.J.Caldwell-Nichols, M. Glugla, S. Gross, R. Lässer, T.L. Le, R.-D. Penzhorn, K.H. Simon
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 617-620
Device, Facility, and Operation | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22662
Articles are hosted by Taylor and Francis Online.
The Tritium Laboratory Karlsruhe (TLK) is developing processes, devices and measurement techniques for the fuel cycle of fusion reactors. Several tritium processing components from tritium operations of experimental and infrastructure facilities of TLK have reached the end of their useful lives, are no longer useable or are to be reconditioned for future use. These components are in the process of post-service examination to determine the condition of the working materials inside these components and the changes that have resulted from operation with hydrogen isotopes, predominantly tritium. Another important aspect is the preparation of some of these components, particularly metal hydride storage beds, for safe disposal. The results are of importance for the design, operation and particularly decommissioning of components of present and future tritium facilities and processing plants, such as JET and ITER. The activities are ongoing and the results to date are presented together with plans for future work.