Demonstration of JK2LB Jacket Fabrication for ITER Central Solenoid

Hamada, K.; Nakajima, Hideo; Kawano, Keiichi; Takano, Katsutoshi; Tsutsumi, F.; Seki, S.; Okuno, K.; Fujitsuna, Nobuyuki; Mizoguchi, M.

doi:10.1109/tasc.2006.873256

Cited by 13 publications

(2 citation statements)

References 4 publications

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“…Alternative materials, low-carbon austenitic steels, have been developed in Europe and Japan. In particular, JK2LB alloy, 70 which was developed by Kobe Steel has been sufficiently characterized for the analysis.…”

Section: Structural Materialsmentioning

confidence: 99%

Fusion Nuclear Science Pathways Assessment

Kessel¹

2012

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This paper reviews US R&D requirements for magnets to be used in a post-ITER fusion machine that would have a nuclear mission. The state of the art of magnets is presented, followed by potential magnet options in the near (< 10 years) and middle term (> 10 years), followed by a description of the different components and system integration issues. The characteristics of an R&D program for investigate these issues is described, followed by a description of the present US facilities.

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Section: Structural Materialsmentioning

confidence: 99%

Fusion Nuclear Science Pathways Assessment

Kessel¹

2012

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“…JK2LB has been demonstrated to sustain reaction heat treatment without significant loss of mechanical properties [13]. Further development is being continued to find optimum chemical compositions so that the material will show the best balance of yield strength and fracture toughness taking account of jacketing and coil fabrication processes consisting of compaction, coil forming and heat treatment [14].…”

Section: B Progress In Jacket Materialsmentioning

confidence: 99%

From CS and TF Model Coils to ITER: Lessons Learnt and Further Progress

Okuno¹,

Nakajima²,

Koizumi³

2006

IEEE Trans. Appl. Supercond.

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Central Solenoid (CS) and Toroidal Field (TF) model coils have been developed in order to establish technologies required to the ITER magnets. All of the development goals have been achieved, including the operation at 13 T, 46 kA and pulsed charging at 1.2 T/s in the CS model coil and the stable operation at 10 T, 80 kA under the ITER relevant stress condition in the TF model coil. Based on these results, further activities are now being performed, in extensive collaboration with industry, to optimize coil designs, to improve performances and to mitigate technical risks during the manufacture of the ITER magnets. One of the activities is to establish production capability of Nb 3 Sn strands having higher critical current density which was redesigned based on the detailed assessment of the conductor performance in the model coil experiments. Strands fulfilling the ITER requirement have successfully been obtained. Another set of activities are full scale manufacturing demonstrations on jacket material for CS and structural materials for TF coil. So far, large forged blocks of JJ1 and ST316LN and thick hot rolled plates of ST316LN were successfully produced as a trial fabrication for the TF coil structures. Experience in the TF model coil indicated a need to improve manufacturing processes for radial plate and a significant progress has also been obtained in this area. Achievements from these activities will provide a firm technical basis for ITER magnet construction including that for industry.

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