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Two hundred and twenty-five papers relevant to fusion technology and engineering were presented at the 27th IAEA Fusion Energy Conference. The ITER project has reached 57.4% of the total construction work scope through to first plasma. Construction of ITER is indeed progressing at full speed, with some ITER components having already been manufactured, such as the toroidal field coil structures and the gyrotrons of the electron cyclotron heating and current drive system, as a result of decades of technological development. Construction of JT-60SA and WEST is also progressing on schedule to support ITER in various engineering and physics aspects. The EU and Japan are advancing with their pre-conceptual designs for DEMO, and the experience and lessons learned from ITER are already being applied to both designs. China reported on the status of the China Fusion Engineering Test Reactor engineering design. One of the technical issues evident from these DEMO designs is the interfacing of the plasma-facing, in-vessel components with plasmas. Advanced plasma-facing elements having liquid metals and an advanced in situ boron coating technology were applied to existing fusion reactors, the results of which were reported at this conference. It was also reported that commissioning of the injector for the International Fusion Materials Irradiation Facility engineering validation and engineering design activities (IFMIF/EVEDA) project has been completed and testing of the Radio Frequency Quadrupole accelerator has begun. Europe and Japan presented their plans to construct neutron irradiation test facilities: the DEMO-Oriented Neutron Source (DONES) and Advanced Fusion Neutron Source (A-FNS), respectively. A new strategy based on a probability-based design method was proposed to mitigate the difficulty of defining the allowable limit for irradiation-induced degradation with limited empirical evidence. [ABSTRACT FROM AUTHOR]

JT-60SA, the largest tokamak that will operate before ITER, has been designed and built jointly by Japan and Europe, and is due to start operation in 2020. Its main missions are to support ITER exploitation and to contribute to the demonstration fusion reactor machine and scenario design. Peculiar properties of JT-60SA are its capability to produce long-pulse, high-β, and highly shaped plasmas. The preparation of the JT-60SA Research Plan, plasma scenarios, and exploitation are producing physics results that are not only relevant to future JT-60SA experiments, but often constitute original contributions to plasma physics and fusion research. Results of this kind are presented in this paper, in particular in the areas of fast ion physics, high-beta plasma properties and control, and non-linear edge localised mode stability studies. [ABSTRACT FROM AUTHOR]

Heating neutral beam (HNB) injectors, necessary to achieve burning conditions and to control plasma instabilities in ITER, are characterized by such demanding parameters that a neutral beam test facility (NBTF) dedicated to their development and optimization is being realized in Padua (Italy) with direct contributions from the Italian government (through Consorzio RFX as the host entity) and the ITER international organization (with kind contributions from the ITER domestic agencies of Europe, Japan and India) and technical and scientific support from various European laboratories and universities. The NBTF hosts two experiments: SPIDER, devoted to ion source optimization for the required source performance, and MITICA, the full-size prototype of the ITER HNB, with an ion source identical to SPIDER. This paper gives an overview of the progress towards NBTF realization, with particular emphasis on issues discovered during this phase of activity and on solutions adopted to minimize the impact on the schedule and maintain the goals of the facilities. The realization of MITICA is well advanced; operation is expected to start in 2023 due to the long procurement time of the in-vessel mechanical components. The beam source power supplies, operating at 1 MV, are in an advanced phase of realization; all high-voltage components have been installed and the complex insulation test phase began in 2018. At the same time, construction and installation of SPIDER plant systems was successfully completed with their integration into the facility. The mechanical components of the SPIDER ion source were installed inside the vessel and connected to the plants. Integrated commissioning with the control, protection and safety systems ended positively and the first experimental phase has begun. The first results of the SPIDER experiment, with data from operational diagnostics, and the plans for the 1 MV insulation tests on the MITICA high-voltage components are presented. [ABSTRACT FROM AUTHOR]