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2025 ANS Winter Conference & Expo
November 8–12, 2025
Washington, DC|Washington Hilton
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My story: Stanley Levinson—ANS member since 1983
Levinson early in his career and today.
As a member of the American Nuclear Society, I have been to many conferences. The International Conference on Probabilistic Safety Assessment and Analysis (PSA ’25), embedded in ANS Annual Meeting in Chicago in June, held special significance for me with the PSA ’25 opening plenary session recognizing the 50th anniversary of the publication of WASH-1400, which helped define my career. Reflecting on that milestone sent me back to 1975, when I was just an undergraduate student studying nuclear engineering at Rensselaer Polytechnic Institute (RPI) in Troy, N.Y., focusing on my mechanics, fluids, and thermodynamic classes as well as my first set of nuclear engineering classes. At that time—and many times since—the question “Why nuclear engineering?” was raised.
Marco Ariola, Alfredo Pironti, Alfredo Portone
Fusion Science and Technology | Volume 36 | Number 3 | November 1999 | Pages 263-277
Technical Paper | doi.org/10.13182/FST99-A107
Articles are hosted by Taylor and Francis Online.
The problem of designing a plasma current and shape control system for a tokamak is dealt with, and a complete framework based on a validated linearized plasma model is developed. Starting from the equilibrium configurations to control and given the required performance, a procedure for choosing the parameters to control is outlined. Then, a method is proposed to evaluate the best performance one could ever expect from a control system, given the actual limitations due to the power supply. A procedure for designing a linear controller is described. The use of a modern multivariable technique, such as the H theory, allows one to take into account the many existing constraints and to find a trade-off among performance, robustness, and control effort. The methodology proposed is general and can be applied in principle to any tokamak plant. The simulation results refer to the International Thermonuclear Experimental Reactor (ITER) tokamak. A controller designed following almost the same steps has been successfully tested on an existing tokamak.