Electromagnetic analysis, structural integrity and progress on mechanical design of the ITER ferromagnetic insert

Morimoto, M.; Ioki, K.; Terasawa, A.; Utin, Y.; Barabash, V.; Gribov, Y.

doi:10.1016/j.fusengdes.2009.02.013

Cited by 11 publications

(3 citation statements)

References 7 publications

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“…In this section we evaluate the measurement errors in ideal and non-ideal geometric configuration of the CER, for a flattop configuration with plasma current I p = 15 MA. The input data, represented by the total field H(r), were obtained with a 3-D numerical model [19][20][21], which implements an iterative procedure based on an integral formulation and includes the ferromagnetic inserts (FI) of ITER [12]. In order to indicate all the considered contributions, the error in non-ideal geometry will be denoted as 2σ(I p + I coils + I FI ), and in similar way in subsequent sections.…”

Section: Kind Of Geometricmentioning

confidence: 99%

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Performance analysis of Rogowski coils and the measurement of the total toroidal current in the ITER machine

et al. 2017

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The paper carries out a comprehensive study of the performances of Rogowski coils. It describes methodologies that were developed in order to assess the capabilities of the Continuous External Rogowski (CER), which measures the total toroidal current in the ITER machine. Even though the paper mainly considers the CER, the contents are general and relevant to any Rogowski sensor. The CER consists of two concentric helical coils which are wound along a complex closed path. Modelling and computational activities were performed to quantify the measurement errors, taking detailed account of the ITER environment. The geometrical complexity of the sensor is accurately accounted for and the standard model which provides the classical expression to compute the flux linkage of Rogowski sensors is quantitatively validated. Then, in order to take into account the non-ideality of the winding, a generalized expression, formally analogue to the classical one, is presented. Models to determine the worst case and the statistical measurement accuracies are hence provided. The following sources of error are considered: effect of the joints, disturbances due to external sources of field (the currents flowing in the poloidal field coils and the ferromagnetic inserts of ITER), deviations from ideal geometry, toroidal field variations, calibration, noise and integration drift. The proposed methods are applied to the measurement error of the CER, in particular in its high and low operating ranges, as prescribed by the ITER system design description documents, and during transients, which highlight the large time constant related to the shielding of the vacuum vessel. The analyses presented in the paper show that the design of the CER diagnostic is capable of achieving the requisite performance as needed for the operation of the ITER machine.

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Section: Kind Of Geometricmentioning

confidence: 99%

“…• approximation of the flux linkage with a discrete sum of fluxes linked with circular turns, • effects of the joints, • effects of nearby ferromagnetic components (the ferromagnetic inserts of ITER [12]), • effects of the eddy currents,…”

Section: Introductionmentioning

confidence: 99%

Performance analysis of Rogowski coils and the measurement of the total toroidal current in the ITER machine

et al. 2017

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“…These losses could result in a large localized heat load on plasma facing components (PFCs), which could make an unacceptable level of heat load damage in ITER machine [3]. Thus ferromagnetic inserts with appropriate SS430 steel in the space between the double walls of the ITER VV (Vacuum Vessel) are going to be used to reduce the value of the TF ripple [4,5]. However, the reduced activation ferritic/martensitic (RAFM) steel, one ferromagnetic material, has been selected as structural material for the six test blanket modules (TBMs) which will be installed and tested in ITER in three dedicated equatorial ports directly facing the * Corresponding author at: Southwestern Institute of Physics, Centre for Fusion, plasma.…”

Section: Introductionmentioning

confidence: 99%