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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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Nuclear Science and Engineering
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Nuclear Technology
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Latest News
ARPA-E announces $40 million to develop transmutation technologies for UNF
The Department of Energy’s Advanced Research Projects Agency–Energy (ARPA-E) announced $40 million in funding to develop cutting-edge technologies to enable the transmutation of used nuclear fuel into less-radioactive substances. According to ARPA-E, the new initiative addresses one of the agency’s core goals as outlined by Congress: to provide transformative solutions to improve the management, cleanup, and disposal of radioactive waste and spent nuclear fuel.
Koichi Uozumi, Takatoshi Hijikata, Takeshi Tsukada, Tadafumi Koyama, Takayuki Terai, Akihiro Suzuki
Nuclear Technology | Volume 188 | Number 1 | October 2014 | Pages 83-96
Technical Paper | Reprocessing | doi.org/10.13182/NT13-49
Articles are hosted by Taylor and Francis Online.
A zeolite column system is under development to realize both a high decontamination factor and high throughput for the treatment of the spent salt generated in the pyroprocessing of the metal fuel cycle. To study the feasibility of the zeolite column system from an engineering aspect, an engineering-scale zeolite column apparatus was installed. Measurements of the superficial velocities of molten salt passing through the columns filled with granular form type-A zeolite at various driving pressures showed that the conventional relationship of the velocity and pressure loss in the components of the apparatus can be useful for the molten salt system. Then, a demonstration test to simulate the decontamination of a fission product, which was represented by cesium, was performed using a zeolite that had been pretreated in aqueous solutions to remove the sodium. Although the absorbed amount of cesium was not as high as previously reported, the concentration of cesium in the effluent salt exhibited a breakthrough curve. Therefore, some of the cesium in the salt was absorbed into the zeolite, and accordingly, the feasibility of the zeolite column system was demonstrated.