Preparation for the ITER Central Solenoid Conductor Manufacturing

Hamada, K.; Nunoya, Y.; Isono, T.; Takahashi, Yoshikazu; Kawano, Keiichi; Saitô, Tôru; Oshikiri, M.; Uno, Y.; Koizumi, N.; Nakajima, Hideo; Matsuda, Hirotaka; Yano, Y.; Devred, A.; Libeyre, P.; Bessette, D.; Jewell, M. C.

doi:10.1109/tasc.2011.2176708

Cited by 21 publications

(6 citation statements)

References 7 publications

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“…The low temperature mechanical measurements included Fatigue Crack Growth Rate (FCGR) on standardized specimens cut from compacted and aged jacket sections. Figure 41 presents a compilation of available and relevant FCGR data for both 316LN and JK2LB jacket sections [111][112][113][114]. The data of Figure 41 clearly show that JK2LB has a slower FCGR than modified 316LN and confirm that it is a more suitable candidate for CS jacket material.…”

Section: Jacket Materialsmentioning

confidence: 94%

Challenges and status of ITER conductor production

Devred

Backbier

Bessette

et al. 2014

Supercond. Sci. Technol.

174

118

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Taking the relay of the Large Hadron Collider (LHC) at CERN, ITER has become the largest project in applied superconductivity. In addition to its technical complexity, ITER is also a management challenge as it relies on an unprecedented collaboration of 7 partners, representing more than half of the world population, who provide 90% of the components as in-kind contributions. The ITER magnet system has a stored energy of 51 GJ and involves 6 of the ITER partners. The coils are wound from Cable-In-Conduit Conductors (CICCs) made up of superconducting and copper strands assembled into a fully transposed, rope-type cable, inserted into a conduit of butt-welded austenitic steel tubes. The conductors for the Toroidal Field (TF) and Central Solenoid (CS) coils require about 500 tons of Nb 3 Sn strands while the Poloidal Field (PF) and Correction Coil (CC) and busbar conductors need around 250 tons of Nb-Ti strands. The required amount of Nb 3 Sn strands far exceeds pre-existing industrial capacity and has called for a significant worldwide production scale up. The TF conductors are the first ITER components to be mass produced and are more than 50% complete. During its life time, the CS coil will have to sustain several tens of thousands of electromagnetic (EM) cycles to high current and field conditions, way beyond anything a large Nb 3 Sn coil has ever experienced. Following a comprehensive R&D program, a technical solution has been found for the CS conductor, which ensures stable performance versus EM and thermal cycling. Productions of PF, CC and busbar conductors are also underway. After an introduction to the ITER project and magnet system, we describe the ITER conductor procurements and the Quality Assurance/Quality Control programs that have been implemented to ensure production uniformity across numerous suppliers. Then, we provide examples of technical challenges that have been encountered and we present a status of ITER conductor production worldwide.

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Section: Jacket Materialsmentioning

confidence: 94%

Challenges and status of ITER conductor production

Devred

Backbier

Bessette

et al. 2014

Supercond. Sci. Technol.

174

118

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“…На JT 60-AS такой толстостенный кондуит сделан, но из стали 316, которая с Nb 3 Sn не совместима, а применение технологии «обжатия» толстой полосой инколоя 908 (как на КСТАР) может встре-тить сложности. Очевидно, лучше сделать квадратный кожух, сваренный из двух половин прямоугольной прокатанной ши-ны, как это сделано в кабеле для ЦС ИТЭР [8].…”

Section: конструкция токонесущего элементаunclassified

Superconducting Magnet System for Russian Tokamak - Fusion Neutron Source Demo-FNS

Ivanov¹,

Anashkin²,

Kolbasov³

2014

PAST-TF

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Приводится описание сверхпроводниковой магнитной системы для проектируемого в России термоядерного источника нейтро-нов -токамака с классическим аспектовым отношением около 3, большим радиусом R = 2,75 м, малым радиусом a = 0,9 м, током плазмы I = 5 МА, магнитным полем на оси B 0 = 5 Тл и B max = 12 Тл. Магнит имеет 18 катушек размером 59 м, ток в каждой из них 3,8 МА, площадь сечения всего 0,2 м 2 . Такая малая площадь катушки связана с необходимостью размещения между плазмой и катушками защиты от радиации толщиной не менее 0,5 м. Очень высокая конструктивная плотность тока j раб = 18 МА/м 2 вдвое выше достигнутой в существующих и строящихся больших магнитах, и высокие механические нагрузки при ограниченной площади для размещения структуры магнита требуют новых технических подходов. На основании проведённых оценок предлагаются следующие решения: поскольку корпус слишком тонок для восприятия действующих сил, ему необходима поддержка жёсткой обмотки из токо-несущих элементов с толстым кожухом, изоляция должна быть только внутри, кабель внутри из плотной плоской скрутки (резерфор-довского типа) из 7-жильных субкабелей, плотно скрученных из проводов на основе ниобий-олова, таких же, как в центральном соленоиде ИТЭР. Предлагаются прокачное охлаждение магнита поперечным потоком гелия низкого давления для эффективного отво-да тепла радиационного нагрева, использование корпуса для снижения напряжения защитного вывода энергии и др. технические реше-ния. Приведены обоснование необходимости и оценки эффективности этих предложений.Ключевые слова: сверхпроводниковый магнит, токамак, источник нейтронов. SUPERCONDUCTING MAGNET SYSTEM FOR RUSSIAN TOKAMAK -FUSION NEUTRON SOURCE DEMO-FNS D.P. Ivanov, I.O. Anashkin, B.N. Kolbasov NRC «Kurchatov Institute», Moscow, RussiaThe paper describes the superconducting magnet system for fusion neutron source based on tokamak with the classic aspect ratio about 3, which is under designing at present in Russia. Plasma major radius plans to be R = 2.75 m, minor one a = 0.9 m, plasma current I = 5 MA, magnetic field on the plasma axis B 0 = 5 T and B max = 12 T. The magnet has 18 coils with dimensions of 5 m  9 m and the current 3,8 MA in each one, while its cross section area is only 0.2 m 2 due to the needs for coils protection from irradiation with the shield thickness not less than 0.5 m. Therefore the constructive current density j = 18 MA/m 2 , which is twice more than in all existed big magnets Very strong forces acting on the coils and very restricted space for magnet structure request new design approaches. The preliminary estimations shows that the case alone is not able to keep the forces acting on it and needs the support of very rigid winding, which should consist from the current carrying elements with thick steel case that has the insulation inside it only; the cable inside it should be flat (Rutherford type), each one from 7 NB 3 Sn wires, like in ITER central solenoid; the cooling by low pressure transverse He flow for effective removal of irradiation heat; the coil case use...

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“…In addition, JAEA has started to fabricate the CS conductors. The details of these conductors are presented in [3][4][5].…”

Section: Development Of Iter Conductors In Japanmentioning

confidence: 99%

Progress of ITER and JT-60SA Magnet Development in Japan

Koizumi¹,

Yoshihiko²,

Yoshida³

et al. 2014

Physics Procedia

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Japan Atomic Energy Agency (JAEA), as the Japan Domestic Agency (JADA), has the responsibility to procure 9 ITER toroidal field (TF) coils, 19 TF coil (TFC) structures, 25% of the TF conductors and 100% of the central solenoid (CS) conductors in ITER and, in addition, CS and equilibrium field (EF) coils including their conductors in JT-60SA, which is being developed as a satellite facility for ITER. In ITER, more than 90% of TF conductor fabrication was completed and finalization of the manufacturing procedure of TF coils is in progress through full-scale trials, such as trial fabrication of dummy double pancakes (DPs). In JT-60SA, fabrication of the EF4 coil was completed and the EF5 and EF6 coils are being assembled.

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Preparation for the ITER Central Solenoid Conductor Manufacturing

Cited by 21 publications

References 7 publications

Challenges and status of ITER conductor production

Challenges and status of ITER conductor production

Superconducting Magnet System for Russian Tokamak - Fusion Neutron Source Demo-FNS

Progress of ITER and JT-60SA Magnet Development in Japan

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