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Fusion Science and Technology
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Extracting efficiency
Craig Piercycpiercy@ans.org
May is a month when we pause—briefly—to recognize something that too often goes unsaid: the extraordinary performance of the existing U.S. nuclear fleet. Capacity factors remain above 90 percent (with a median of 91.29 for the three-year period 2023–2025—see Nuclear News, May 2026, p. 24), an impressive figure delivered at a scale unmatched anywhere else on the globe. That level of sustained output is not an accident of design; it is a daily achievement. It reflects the discipline, professionalism, and pride of the men and women who operate and maintain these facilities, often without fanfare.
In this issue, you will also read about the important work researchers at our national laboratories are doing to extract even greater efficiency from the plants we already have. That effort deserves more attention, because it points to a fundamental truth: the fastest, most reliable way to expand nuclear generation in the United States is not solely through new builds—it is by maximizing the assets already on the grid.
R. Albanese, M. De Magistris, R. Fresa, F. Maviglia, S. Minucci
Fusion Science and Technology | Volume 68 | Number 4 | November 2015 | Pages 741-749
Technical Paper | doi.org/10.13182/FST15-127
Articles are hosted by Taylor and Francis Online.
We consider the problem of the accurate tracing of long magnetic field lines in tokamaks, which is in general crucial for the determination of the plasma boundary as well as for the magnetic properties of the scrape-off layer. Accurate field line tracing is strictly related to basic properties of ordinary differential equation (ODE) integrators, in terms of preservation of invariant properties and local accuracy for long-term analysis. We introduce and discuss some assessment criteria and a procedure for the specific problem, using them to compare standard ODE solvers with a volume-preserving algorithm for given accuracy requirements. In particular, after the validation for an axisymmetric plasma, a three-dimensional (3-D) configuration is described by means of Clebsch potentials, which provide analytical invariants for assessing the accuracy of the numerical integration. A standard fourth-order Runge-Kutta routine at fixed step is well suited to the problem in terms of reduced computational burden, with extremely good results for accuracy and volume preservation. Then we tackle the problem of field line tracing in the determination of plasma-wall gaps for a 3-D configuration, demonstrating the effective feasibility of the plasma boundary evaluation in tokamaks by tracing field lines with standard tools.