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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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U.S. nuclear supply chain: Ready for liftoff
Craig Piercycpiercy@ans.org
This month, September 8–11, the American Nuclear Society is teaming up with the Nuclear Energy Institute to host our first-ever Nuclear Energy Conference and Expo—NECX for short—in Atlanta. This new meeting combines ANS’s Utility Working Conference and NEI’s Nuclear Energy Assembly to form what NEI CEO Maria Korsnick and I hope will be the premier nuclear industry gathering in America.
We did this because after more than four decades of relative stagnation, the U.S. nuclear supply chain is finally entering a new era of dynamic growth. This resurgence is being driven by several powerful and increasingly durable forces: the explosive demand for electricity from artificial intelligence and data centers, an unprecedented wave of public and private acceptance of—and investment in—advanced nuclear technologies, and a strong market signal for reliable, on-demand power. Add the recent Trump administration executive orders on nuclear into the mix, and you have all the makings of an accelerant-rich business environment primed for rapid expansion.
Yassin A. Hassan, Andrey A. Troshko
Nuclear Technology | Volume 119 | Number 1 | July 1997 | Pages 29-37
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT77-A35392
Articles are hosted by Taylor and Francis Online.
The thermal-hydraulic CATHARE V1.3U code has been used to simulate an International Standard Problem (ISP38) experiment conducted at BETHSY Integral Test Facility located in Grenoble, France. This experiment presents simulation of the loss of residual heat removal system during midloop operation. It involved opening of the pressurizer man way and steam generator outlet plenum man way simultaneously with switching on the heating rod power to simulate the decay heat. The total power level of 138 kW was kept unchanged throughout the test. Mass discharge through both manways led to core boiling and uncovery. The test was stopped when the primary cooling system was filled back to a midloop level. Overall, the code’s prediction and experimental data were found to be in reasonable qualitative agreement. However, the code underestimated the time of the core uncovery and the actuation of the gravity feed injection because of the overprediction of the discharge through the steam generator man way during the initial stage of the transient. This was caused by misestimation of the phase separation effect at the hot leg/surge line tee junction and significant water entrainment into the surge line at the beginning of the test. It was found that the upward tee junction model needs to be refined for the low-pressure transients.