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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Fusion Science and Technology
Latest News
Disa seeks NRC license for its uranium mine waste remediation tech
The Nuclear Regulatory Commission has received a license application from Disa Technologies to use high-pressure slurry ablation (HPSA) technology for remediating abandoned uranium mine waste at inactive mining sites. Disa’s headquartersin are Casper, Wyo.
D. Demange, I. Cristescu, E. Fanghänel, M. Glugla, N. Gramlich, T.L. Le, R. Michling,H. Moosmann, W.M. Shu, K.H. Simon, R. Wagner, S. Welte, R.S Willams
Fusion Science and Technology | Volume 67 | Number 2 | March 2015 | Pages 312-315
Proceedings of TRITIUM 2013 | doi.org/10.13182/FST14-T18
Articles are hosted by Taylor and Francis Online.
The CAPER facility of the Tritium Laboratory Karlsruhe has demonstrated the technology for the tokamak exhaust processing. CAPER has been significantly upgraded to pursue R&D towards highly tritiated water (HTW) handling and processing. The preliminary tests using a metal oxide reactor producing HTW afterward detritiated with PERMCAT were successful. In a later stage, a micro-channel catalytic reactor was installed in view of long term R&D program on HTW. The integration of this new system in CAPER was carried out along with a careful safety analysis due to high risk associated with such experiments. First experiments using the μ-CCR were performed trouble free, and HTW up to 360 kCi/kg was produced at a rate of 0.5 g/h. Such HTW was collected into a platinized zeolite bed (2 g of HTW for 20 g of Pt-zeolite), and in-situ detritiation was performed via isotopic exchange with deuterium. These first experimental results with tritium confirmed the potential for the capture and exchange method to be used for HTW in ITER.