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This work reviews the further development of the Italian–Russian bilateral project IGNITOR. One of the primary tasks for the execution of the project is the determination of the different types of engineering systems that will be required to support the engineering infrastructure of the IGNITOR tokamak. The tritium fuel cycle and detritiation systems, which provide tritium reprocessing and confinement during the operation of the scientific program, will be the most important systems. For the location of the IGNITOR, Russia proposed the Troitskii Institute and Thermonuclear Research (TRINITI) site near Moscow. The scope of this work is the investigation of the engineering concept of the tritium fuel cycle and detritiation systems for air and water with regard to the operation of the IGNITOR with tritium plasma at the TRINITI site. • Technological capabilities for IGNITOR tokamak fusion reactor were reviewed. • Optimised configuration of fuel cells for IGNITOR was proposed. • Replacement gas chromatography is ideal for hydrogen isotope separation. • Proposed to use CECE technology for water detritiation. • Proposed to carry out gas stream detritiation using of scrubber column. [ABSTRACT FROM AUTHOR]

At present, the T-15MD tokamak is being built and its supporting technological systems are being modernized at the National Research Center Kurchatov Institute in the framework of the federal target-oriented program "New Generation Nuclear Power Technologies in 2010–2015 and in Prospect to 2020." The T-15MD magnet system is to ensure producing and confinement of hot plasma in the divertor configuration. The T-5MD plasma parameters are as follows: major radius R0 = 1.48 m, minor radius a = 0.67 m, elongation k95 = 1.7–1.9, triangularity δ95 = 0.3–0.4, plasma current Ip = 2 MA, and toroidal magnetic field at the plasma axis BTO = 2 T. The tokamak will be equipped with an auxiliary plasma heating and current drive system (Paux = 15–20 MW), which will enable achieving a high plasma temperature (Ti ~ Te of 5–9 keV) and a plasma density (ne ≈ 1020 m–3) during a discharge with a pulse duration of up to 30 s. The magnet system includes a toroidal winding and a poloidal magnet system. The poloidal magnet system may generate the one- or two-null divertor magnetic configuration. The power supply system provides the necessary current scenarios in the magnet system windings. The T-15MD magnet together with the vacuum vessel was pre-assembled at the NPO GKMP Ltd. plant in Bryansk. All elements of the magnet system and the vacuum vessel are delivered to the National Research Center Kurchatov Institute in Moscow, where the T-15MD tokamak will be assembled. The technological systems are to be reconstructed by the end of 2019. The physical start-up of the T-15MD is scheduled for December 2020. [ABSTRACT FROM AUTHOR]

• T-15MD project is the initial technical base for creating fusion neutron source for atomic energy needs. • The preassembly of the tokamak T-15MD magnet system together with the vacuum vessel was completed. • Most of tokamak systems were manufactured and preliminary tested before the final assembly of tokamak. • All the diagnostic equipment is available and part of it was used in experiments on tokamak T-10. • Physical start-up T-15MD is scheduled for December 2020 year. At the present time, in the NRC Kurchatov Institute under the auspices of the Federal Target Program "Nuclear energy-technologies of new generation for period 2010–2015 and to the prospect until 2020" the tokamak T-15MD and supporting facilities are being built. The preassembly of the tokamak T-15MD magnet system together with the vacuum vessel was completed at a plant in Bryansk. All elements of the magnet system and vacuum vessel have been delivered to the NRC "Kurchatov Institute" in Moscow for the tokamak T-15MD assembly. It is expected that the T-15MD assembly will be completed in March of 2019. The reconstruction of the sub-station 110/10/04 kV for own needs was completed in 2017 and the reconstruction of the main sub-station 110/10/1 kV, 300 MW was completed in 2018. Twenty- two of the new transformers 10/1 kV and 20 new thyristor convertors will be installed during 2018–2019 period. One gyrotron with output power 1 MW for pre-ionization should be installed in 2019. Tokamak T-15MD connection to water and electrical communication and also the adjustment of control system will be completed in the middle of 2020. Physical start-up T-15MD is scheduled for December 2020 year. [ABSTRACT FROM AUTHOR]

The IGNITOR tokamak project is one of main directions of scientific collaboration between Russia and Italy. The project is entering the stage of technical design for the location of the machine at the TRINITI site in Troitsk of the Moscow region. The IGNITOR machine differs considerably from other machines based on the tokamak concept by using a super strong magnetic field (13 T) and plasma current (11 MA). It will operate with short pulses (of approximately 10 s in length) and will not have a tritium breeding blanket. The requirements of the tritium fuel cycle are high because three tritium pulses per day are foreseen with a total amount of approximately 10 g to be processed daily. Fuelling will be based on gas injection. It necessary to provide a full tritium processing cycle including the storage and supply of the tritium, plasma exhaust purification, separation of the hydrogen isotopes, detritiation of gaseous and water streams, and tritium recovery from the plasma facing components. This paper considers tritium storage and delivery system as part of the fuel cycle. [ABSTRACT FROM AUTHOR]

The tokamak Ignitor is one of the main long-term projects involving scientific cooperation between Russian Federation and Italian Republic. Currently, negotiations are underway to develop the Ignitor Technical Design Project with on-site placement at site of the experimental bench complex "Tokamak with Strong Field" (complex TSP) of the Joint Stock Company "State Research Centre of Russian Federation TRINITI" (TRINITI) Moscow, Troitsk. The Ignitor project differs significantly from present-day experimental fusion tokamak reactors, having a strong magnetic field (13 T), in which the pulse discharge (about 10 s) flows a powerful discharge current (11MA). Ohmic heating is the main mechanism for ignition of the fusion reaction. During inspection of the current state of equipment and communications of all the main elements of the power and engineering infrastructure of the complex TSP, including stationary and pulsed power supply systems, the vacuum, cryogenic, and fuel systems and diagnostic complex were analyzed. Based on a comparison of the requirements of the Ignitor project to the site location infrastructure, involving from published sources technical characteristics and requirements for livelihood systems of the Ignitor tokamak the technical proposals for modernization of the complex TSP under IGNITOR project task were prepared. [ABSTRACT FROM AUTHOR]

This paper describes a conceptual ICRH system for the tokamak T-15MД, in construction at the Nuclear Fusion Institute of the Kurchatov Research Centre for Atomic Energy in Moscow. The proposed system consists of a number of Travelling Wave Antenna sections, located below the equatorial plane of the tokamak. This antenna system, loaded by a simulated density profile provided by the T-15MД team, is modelled including its resonant ring feeding system. Resonant ring feeding allows the recirculation of the RF power that is not radiated to the plasma and the termination of the TWA section on its iterative impedance. The paper describes the antenna design, the feeding ring tuning algorithm and expected performances of this antenna concept. The chosen geometry of the TWA sections is compatible with that of a future reactor and therefore this ICRH antenna system for T-15MД represents also a test bed for DEMO. [ABSTRACT FROM AUTHOR]