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Centrus, X-energy sign enrichment contract as TRISO-X expands TX-1 campus
Centrus Energy Corp. will be providing X-energy with enrichment services for low-enriched uranium and high-assay, low-enriched uranium to support X-energy’s planned deployments of Xe-100 small modular reactors and TRISO-X fuel, according to the terms of a new contract signed by the companies. The fuel will be produced at Centrus’s American Centrifuge Plant in Piketon, Ohio. In turn, X-energy will provide Centrus with prepayments to help support expanding the capacity of Centrus’s domestic commercial enrichment program.
K. Nagarajan, T. Subramanian, B. Prabhakara Reddy, P. R. Vasudeva Rao, Baldev Raj
Nuclear Technology | Volume 162 | Number 2 | May 2008 | Pages 259-263
Technical Note | First International Pyroprocessing Research Conference | doi.org/10.13182/NT08-A3954
Articles are hosted by Taylor and Francis Online.
Reducing the cooling time of spent fast breeder reactor (FBR) fuel, thus reducing the doubling time and introducing metallic fuels into FBRs, is essential for meeting the increasing energy demand of India. Development of pyrochemical reprocessing technology for processing the spent FBR fuels is another prerequisite. Accordingly, studies on the molten salt electrorefining process for metallic fuels and the oxide electrowinning process for oxide fuels have been carried out at the Indira Gandhi Centre for Atomic Research, Kalpakkam. A laboratory-scale argon atmosphere facility for molten salt electrorefining process studies is operational. Using this facility, studies on all the unit operations of the process have been carried out on uranium alloys. A code, PRAGAMAN, based on thermochemical modeling has been developed to simulate the electrotransport behavior of elements during the electrorefining process. Based on our studies, the eutectic MgCl2-NaCl-KCl ternary salt has been proposed as the alternate electrolyte for the conventional 2CsCl-NaCl electrolyte for oxide processing. A facility to demonstrate the remotization of all the process steps of the molten salt electrorefining process flow sheet for metallic fuels at 1- to 3-kg scale is being set up. Basic electrochemical studies on the reduction behavior of the chlorides and oxychlorides of uranium and the lanthanides in molten salts have also been carried out. This paper describes the studies carried out so far and the plans for the near future.