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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.
Joo Hwan Park, Jee-Won Park, Hangbok Choi, Myung Seung Yang
Nuclear Technology | Volume 153 | Number 2 | February 2006 | Pages 164-174
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3697
Articles are hosted by Taylor and Francis Online.
Thermal-hydraulic compatibility of the DUPIC fuel bundle with a 713-MW(electric) Canada deuterium uranium (CANDU-6) reactor was studied by using both the single-channel and subchannel analysis methods. The single-channel analysis provides the fuel channel flow rate, pressure drop, critical channel power, and the channel exit quality, which are assessed against the thermal-hydraulic design requirements of the CANDU-6 reactor. The single-channel analysis by the NUCIRC code showed that the thermal-hydraulic performance of the DUPIC fuel is not different from that of the standard CANDU fuel. Regarding the local flow characteristics, the subchannel analysis also showed that the uncertainty of the critical channel power calculation for the DUPIC fuel channel is very small. As a result, both the single- and subchannel analyses showed that the key thermal-hydraulic parameters of the DUPIC fuel channel do not deteriorate compared with the standard CANDU fuel channel.
