Status of R&amp;D activity for ITER ICRF power source system

Mukherjee, Aparajita; Trivedi, Rajesh; Singh, Raghuraj; Rajnish, Kumar; Machchhar, H.; Ajesh, P.; Suthar, Gajendra; Soni, Dipal; Patel, Manoj; Mohan, Kartik; Hari, Jvs; Anand, Rohit; Verma, Sriprakash; Agarwal, Rohit; Jha, Akhil; Kazarian, F.; Beaumont, B.

doi:10.1016/j.fusengdes.2015.05.007

Cited by 24 publications

(6 citation statements)

References 3 publications

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“…Forward power could be kept constant at 1.5 MW, with reflection levels of 11%, thereby demonstrating a VSWR of 2:1, which creates an important database for ITER. The Diacrode has been subjected to a burn test for 6000 s continuously to verify the ruggedness and benchmark the technology for fusion applications [2]. The electrical efficiency of a complete RF chain is around 55% (on a mismatched load)-65% (on a matched load).…”

Section: Ion Cyclotron (Ic) Rf Systemsmentioning

confidence: 99%

Progress of ITER-India activities for ITER deliverables—challenges and mitigation measures

et al. 2019

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The responsibilities of ITER-India include a mix of precision, heavy, R&D intensive and interface intensive systems, under the built-to-print and functional systems categories. In several systems, the components are the first or largest of their kind. The uniqueness of component specifications and adherence to the desired quality standards considering the harsh nuclear environment in which the components need to operate and survive the lifetime of ITER leads to a challenging situation—namely that neither the existing laboratories nor potential suppliers have ever done or encountered such a scale-up (either in size, capacity, precision, quality etc) and in many cases do not have even the research and development (R&D) infrastructure to match ITER’s requirements. To bridge this gap, ITER-India adopted a two-step approach of first manufacturing prototypes as per ITER-specific standards and then subjecting them all to critical evaluation before launching bulk production. Some of the key areas of development include demonstrations of the following: (a) 1.5 MW radiofrequency power in the 35–65 MHz frequency range under Diacrode and Tetrode tube technologies for the ion cyclotron resonance heating system; (b) a low loss multi-process pipe cryogenic transfer line and the development of a 3.3 kg s−1 cold circulator for the cryoline and cryo-distribution system; (c) an angled accelerator grid with precision in positioning of apertures within 50 μm, as a first of its kind development, and special, ITER grade, copper alloy development for the diagnostic neutral beam (DNB) system. Full scale test facilities have been built for the performance assessment of the DNB, the electron cyclotron and ion cyclotron sources, cryogenic transfer lines and diagnostics systems. A summary is presented of the technical features of the major areas of procurements, notable achievements in R&D and manufacturing and their application in the Indian R&D related to fusion.

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Section: Ion Cyclotron (Ic) Rf Systemsmentioning

confidence: 99%

Progress of ITER-India activities for ITER deliverables—challenges and mitigation measures

et al. 2019

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“…Several new developments are implemented in the design of this antenna system, and we summarize here briefly a few of them. For a full and detailed overview we refer the reader to [64][65][66][67].…”

Section: New Antenna Concepts In View Of Itermentioning

confidence: 99%

Recent advances in physics and technology of ion cyclotron resonance heating in view of future fusion reactors

Ongena

Messiaen

Kazakov

et al. 2017

Plasma Phys. Control. Fusion

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Ion temperatures of over 100 million degrees need to be reached in future fusion reactors for the deuterium-tritium fusion reaction to work. Ion cyclotron resonance heating (ICRH) is a method that has the capability to directly heat ions to such high temperatures, via a resonant interaction between the plasma ions and radiofrequency waves launched in the plasma. This paper gives an overview of recent developments in this field. In particular a novel and recently developed threeion heating scenario will be highlighted. It is a flexible scheme with the potential to accelerate heavy ions to high energies in high density plasmas as expected for future fusion reactors. New antenna designs will be needed for next step large future devices like DEMO, to deliver steadystate high power levels, cope with fast variations in coupling due to fast changes in the edge density and to reduce the possibility for impurity production. Such a new design is the traveling wave antenna (TWA) consisting of an array of straps distributed around the circumference of the machine, which is intrinsically resilient to edge density variations and has an optimized power coupling to the plasma. The structure of the paper is as follows: to provide the general reader with a basis for a good understanding of the later sections, an overview is given of wave propagation, coupling and RF power absorption in the ion cyclotron range of frequencies, including a brief summary of the traditionally used heating scenarios. A special highlight is the newly developed three-ion scenario together with its promising applications. A next section discusses recent developments to study edge-wave interaction and reduce impurity influx from ICRH: the dedicated devices IShTAR and Aline, field aligned and three-strap antenna concepts. The principles behind and the use of ICRH as an important option for first wall conditioning in devices with a permanent magnetic field is discussed next. The final section presents ongoing developments for antenna systems in next step devices like ITER and DEMO, with as highlight the TWA concept.

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“…Nine RF sources (eight plus one spare) will be procured by INDA, and their development program is actively proceeding [4]. In this program, the Thales Diacrode tube TH 628 and the EIMAC Tetrode tube 4CM2500KG will be tested against the ITER specifications.…”

Section: High Power Rf Sourcesmentioning

confidence: 99%

Status of the ITER ion cyclotron heating and current drive system

Lamalle

Beaumont

Kazarian

et al. 2015

AIP Conference Proceedings

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Abstract. The paper reports on latest developments for the ITER Ion Cyclotron Heating and Current Drive system: imminent acceptance tests of a prototype power supply at full power; successful factory acceptance of candidate RF amplifier tubes which will be tested on dedicated facilities; further design integration and experimental validation of transmission line components under 6MW hour-long pulses. The antenna Faraday shield thermal design has been validated above requirements by cyclic high heat flux tests. R&D on ceramic brazing is under way for the RF vacuum windows. The antenna port plug RF design is stable but major evolution of the mechanical design is in preparation to achieve compliance with the load specification, warrant manufacturability and incorporate late interface change requests. The antenna power coupling capability predictions have been strengthened by showing that, if the plasma scrape-off layer turns out to be steep and the edge density low, the reference burning plasma can realistically be displaced to improve the coupling.

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Status of R&D activity for ITER ICRF power source system

Cited by 24 publications

References 3 publications

Progress of ITER-India activities for ITER deliverables—challenges and mitigation measures

Progress of ITER-India activities for ITER deliverables—challenges and mitigation measures

Recent advances in physics and technology of ion cyclotron resonance heating in view of future fusion reactors

Status of the ITER ion cyclotron heating and current drive system

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