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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
Argonne researching “climate-ready” nuclear plant design
Scientists at Argonne National Laboratory have partnered with Washington state–based Energy Northwest to look at alternative ways to cool nuclear reactors as climate change impacts relied-upon water sources.
Yoshiharu Sakamura, Masatoshi Iizuka, Tadafumi Koyama, Shinichi Kitawaki, Akira Nakayoshi
Nuclear Technology | Volume 190 | Number 2 | May 2015 | Pages 193-206
Technical Paper | Reprocessing | doi.org/10.13182/NT14-64
Articles are hosted by Taylor and Francis Online.
A novel approach to extracting transuranic elements (TRUs) from molten salt into liquid Cd using U metal as a reductant was investigated for the molten salt electrorefining process. We considered two methods of adding U metal: direct extraction (DE) and electrochemical extraction (EE). In the DE method, U metal added to Cd is dissolved and exchanged for TRU ions in the salt. The EE method is based on the principle of a concentration cell. When U metal and Cd separately placed in the salt are electrically connected, the U metal is anodically dissolved in the salt, and U and TRU ions are reduced at the Cd. The advantages of these methods over the conventional electrolytic method are as follows: The container for Cd can be made of steel, dendritic U metal does not form on the surface of the Cd or the crucible, and the operation is simple and stable. It was experimentally demonstrated that Pu and Am could be extracted from LiCl-KCl melt into liquid Cd by both the DE and EE methods when U metal collected at the solid cathode was used as a reductant. Crucibles made of steel could be used as containers for Cd, and a total of ∼3 wt% of U, Pu, and Am in the Cd was collected in 10 h. In the EE tests, the separation factors among U, Pu, and Am were always equal to the values at equilibrium. The rate-determining step for the extraction was not the mass transfer in the Cd or salt phase but the electron transfer at the Cd-salt interface. Then, a concept high-performance electrorefiner equipped with two anode–solid cathode modules and an EE or DE module was preliminarily designed.