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Quantitative Evaluation of Fatigue Impact on CS and TF Coils in Pulsed Tokamak Power Plant

Toshihiro HAMADA, Kunihiko OKANO¹⁾ and Ryoji HIWATARI

The University of Tokyo, Kashiwa-shi, Chiba 277-8568, Japan

1)

Central Research Institute of Electric Power Industry, Komae-shi, Tokyo 201-8511, Japan

(Received 28 November 2013 / Accepted 1 March 2014 / Published 31 October 2014)

Abstract

Fatigue issue of a pulsed operation tokamak is studied for the major radii R_p = 10 m, 11 m and 12 m in this paper. By study of central solenoid coil (CS) fatigue, it is clarified that pulse cycle number of the reference of 10 m throughout 30-year operation period is about 50,000 and its allowable stress amplitude for CS fatigue is about 300 MPa. This constraint has actually no impact on the CS designs of the reference tokamaks. Allowable length of toroidal field coil (TFC) maintenance port of the reference 10 m tokamak is calculated to be 13.3 m, which is corresponding to 92 % of TFC height. Also the minimum width of each cryostat post which supports the overturning force of TFC is found to be 2.3 m to prevent its fracture. This result indicates that fatigue may have impact on rather outer support structure of TFC than TFC itself. This construction cost for strengthening cryostat post could reach a few of hundreds million dollars according to a rough calculation.

Copyright (c) 2014 The Japan Society of Plasma Science and Nuclear Fusion Research

Keywords

fatigue life curve, pulsed tokamak reactor, pulse duration, CS, central solenoid coil, TFC, toroidal field coil, equivalent alternating stress, Modified-Goodman Diagram

DOI: 10.1585/pfr.9.3405138

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References

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This paper may be cited as follows:

Toshihiro HAMADA, Kunihiko OKANO and Ryoji HIWATARI, Plasma Fusion Res. 9, 3405138 (2014).