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Fusion Science and Technology
Latest News
PPPL develops framework for unifying tokamak ML control models
Princeton Plasma Physics Laboratory announced that researchers at the lab, in collaboration with Princeton University, have developed a general algorithm for prediction and control in tokamak systems and have tested it at DIII-D, as presented in a recent Nuclear Fusion paper.
According to the paper, most machine learning (ML)–based tools for use in fusion machines have been implemented as stand-alone demonstrations, aiming to predict the plasma profile, suppress a form of instability, for example. PPPL’s project provides a framework that aims to accommodate these disparate models into an integrated system, which the team calls PACMAN (Prediction and Control Using Machine Learning).
Takeo Nishitani, Mikio Enoeda, Masato Akiba, Toshihiko Yamanishi, Kimio Hayashi, Hiroyasu Tanigawa
Fusion Science and Technology | Volume 52 | Number 4 | November 2007 | Pages 971-978
Technical Paper | Tritium, Safety, and Environment | doi.org/10.13182/FST07-A1620
Articles are hosted by Taylor and Francis Online.
Japan Atomic Energy Agency (JAEA) plays a role of the principal institute in Japan for the design and the development of a solid breeder (WCSB) blanket and a helium cooled solid breeder (HCSB) blanket, in the ITER Test Blanket Modules (TBM) programt. The WCSB and HCSB modules consist of reduced activation ferritic/martensitic steel, F82H, as the structural material, Li2TiO3 as the tritium breeder material, beryllium or Be-Ti alloy as the neutron multiplier. One of the R&Ds for the WCSB TBM, the mockup of the first wall with embedded cooling channels was fabricated by applying HIP technique. Pebbles of Be12Ti, which is a candidate material for the advanced neutron multiplier, were produced by a small-scale rotating electrode method. Mechanical and chemical properties and irradiation effects have been studied for Be12T pebbles. Both oxidation and steam interaction were about 1/1000 as small as those of beryllium metal, which indicates a possibility to reduce a risk of a water or air ingress accident. The test schedule of TBMs is discussed according to the ITER operation phases.
