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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
Yasuhisa Oya, Misaki Sato, Kenta Yuyama, Masanori Hara, Yuji Hatano, Masao Matsuyama, Takumi Chikada
Fusion Science and Technology | Volume 68 | Number 2 | September 2015 | Pages 358-361
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-931
Articles are hosted by Taylor and Francis Online.
Dynamics of tritium recovery using CuO catalyst and water bubbler was studied as a function of gas flow rate and CuO temperature. The rate constant of tritiated water formation by CuO catalyst at the temperature above 500 K was determined to be k [s-1] = 5.4×105 exp (-0.65 eV / kBT). For the flow rate less than 50 sccm, it was found that the reaction rate will be controlled by the desorption rate of HTO on the surface of CuO. These results were applied for the design of tritium removal system at radiation-controlled area. It was concluded that the reactor tubing with 1.0 meter length at 600 K will be suitable to reduce the tritium concentration less than 1/1000 and the longer reactor tubing will be required if the operation temperature will be lower than 600 K.