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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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The journey of the U.S. fuel cycle
Craig Piercycpiercy@ans.org
While most big journeys begin with a clear objective, they rarely start with an exact knowledge of the route. When commissioning the Lewis and Clark expedition in 1803, President Thomas Jefferson didn’t provide specific “turn right at the big mountain” directions to the Corps of Discovery. He gave goal-oriented instructions: explore the Missouri River, find its source, search for a transcontinental water route to the Pacific, and build scientific and cultural knowledge along the way.
Jefferson left it up to Lewis and Clark to turn his broad, geopolitically motivated guidance into gritty reality.
Similarly, U.S. nuclear policy has begun a journey toward closing the U.S. nuclear fuel cycle. There is a clear signal of support for recycling from the Trump administration, along with growing bipartisan excitement in Congress. Yet the precise path remains unclear.
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.
