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Westinghouse teams with Nordion and PSEG to produce Co-60 at Salem
Westinghouse Electric Company, Nordion, and PSEG Nuclear announced on Tuesday the signing of long-term agreements to establish the first commercial-scale production of cobalt-60 in a U.S. nuclear reactor. Under the agreements, the companies are to apply newly developed production technology for pressurized water reactors to produce Co-60 at PSEG’s Salem nuclear power plant in New Jersey.
Rodrigo Antunes, Laëtitia Frances, Marco Incelli, Alessia Santucci
Fusion Science and Technology | Volume 76 | Number 3 | April 2020 | Pages 257-261
Technical Paper | doi.org/10.1080/15361055.2019.1705748
Articles are hosted by Taylor and Francis Online.
One of the reference technologies for the fuel cycle of fusion machines is Pd/Ag membranes. This technology is proposed to be implemented in tritium recovery systems because of their exclusive selectivity toward molecular hydrogen isotopes (Q = H, D, T). To perform scaling-up studies for the Tritium Extraction and Removal System of the European DEMOnstration fusion power reactor (DEMO) with a solid blanket, a one-dimensional simulation code was recently developed and successfully validated with experiments. This code relies on different operational (e.g., feed pressure and temperature), geometrical (e.g., permeator length), and membrane-intrinsic (e.g., Q2 permeability) parameters given as input. The main outcome is the Q2 permeation efficiency, defined as the Q2 permeate–to–feed flow ratio. Because of the low concentrations of Q2 expected at the He stream purging the solid blanket, the surface effects are expected to be important, decreasing the separation efficiency of the Pd/Ag permeators. In this paper the role of surface effects on the permeation efficiency is studied for a DEMO-relevant scenario (feeding mixture: HT/H2/He). Moreover, a sensitivity study is also given demonstrating the high impact of the permeation area, temperature, and feed pressure on the permeation efficiency of HT.