General and crevice corrosion study of the in-wall shielding materials for ITER vacuum vessel

Joshi, Kaivalya S.; Pathak, H.A.; Dayal, R. K.; Bafna, V.K.; Ioki, K.; Barabash, V.

doi:10.1088/1742-6596/390/1/012038

Cited by 2 publications

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“…R&D was carried out to establish the impact of corrosion on the materials of these blocks, as these blocks remain immersed in water at a high temperature and pressure and are inaccessible due to their permanent placement in between the walls of the vacuum vessel [18]. The corrosion study shows that there is no significant pitting under conditions of a water temperature of 100 °C and 1.1 MPa pressure, whereas pitting is evidenced with operating conditions of a 200 °C water temperature and pressures of 2.4 MPa.…”

Section: In-wall Shield (Iws)mentioning

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: In-wall Shield (Iws)mentioning

confidence: 99%

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

et al. 2019

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“…These blocks remain immersed in water passed through double wall of vacuum vessel to maintain vacuum vessel temperature at 200°C during backing and 100°C during plasma operation. Corrosion properties of IWS materials under these operating conditions have been studied and found acceptable [3].…”

Section: Prsmentioning

confidence: 99%

Manufacturing of ITER vacuum vessel In-Wall Shielding

Pathak

Raval

Phull

et al. 2013

2013 IEEE 25th Symposium on Fusion Engineering (SOFE)

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ITER vacuum vessel is a double comprising of inner and outer shells. Space betw is filled up with ITER vacuum vessel In-Wall S to, (i) provide neutron shielding to toroidal mag and (ii) reduce toroidal magnetic field ripple. T 8960 IWS blocks of different sizes, shapes distributed over nine vessel sectors and corre field joints. Manufacturing of IWS requires va like water jet cutting, precision CNC machining tight tolerances, accurate dimension measu welding, full penetration welding, Non Destruct Various IWS mock ups are manufactured to validate manufacturing and inspection pro sufficient experience gained from manufacturin mock ups, final manufacturing of IWS has s Avasarala Technologies Limited, India. This p important features of IWS design, results manufacturing, optimization of manufacturing processes, assembly and progress of manufacturing. Keywords-IWS, Ferromagnetic inserts, neu toroidal magnetic field ripple, borated steel, crevicI.

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General and crevice corrosion study of the in-wall shielding materials for ITER vacuum vessel

Cited by 2 publications

References 0 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

Manufacturing of ITER vacuum vessel In-Wall Shielding

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