Test of the ITER central solenoid model coil and CS insert

Martovetsky, N.; Michael, Philip; Minervini, J.V.; Radovinsky, A.; Takayasu, M.; Gung, C.; Thome, R.J.; Ando, T.; Isono, T.; Hamada, K.; Kato, Takashi; Kawano, Keiichi; Koizumi, N.; Matsui, K.; Nakajima, Hideo; Nishijima, G.; Nunoya, Y.; Sugimoto, M.; Takahashi, Yoshikazu; Tsuji, Hiroshi; Bessette, D.; Okuno, K.; Mitchell, N.; Ricci, M.; Zanino, Roberto; Savoldi, Laura; Arai, K.; Ninomiya, A.

doi:10.1109/tasc.2002.1018475

Cited by 80 publications

(56 citation statements)

References 5 publications

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“…Further details on the coil design [6], strand and cable manufacturing [7]- [11], coil manufacturing [12], short sample test results [5], [13], and supporting analyses to the insert test [14]- [17] can be found in the extensive list of references quoted. [19], [20], with the necessary adaptations to the different operating conditions and PF conductor characteristics [15]. Besides the obvious characterization of the DC and AC conductor performance once wound in a coil of relevant length and size, the main test focus was on the following items:…”

Section: The Pf Conductor Insertmentioning

confidence: 99%

Test Results From the PF Conductor Insert Coil and Implications for the ITER PF System

Bessette

Bottura

Devred

et al. 2009

IEEE Trans. Appl. Supercond.

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Abstract-In this paper we report the main test results obtained on the Poloidal Field Conductor Insert coil (PFI) for the International Thermonuclear Experimental Reactor (ITER), built jointly by the EU and RF ITER parties, recently installed and tested in the CS Model Coil facility, at JAEA-Naka. During the test we (a) verified the DC and AC operating margin of the NbTi Cable-in-Conduit Conductor in conditions representative of the operation of the ITER PF coils, (b) measured the intermediate conductor joint resistance, margin and loss, and (c) measured the AC loss of the conductor and its changes once subjected to a significant number of Lorentz force cycles. We compare the results obtained to expectations from strand and cable characterization, which were studied extensively earlier. We finally discuss the implications for the ITER PF system. Index Terms-Cable-in-conduit conductors, fusion reactors, Nb-Ti superconducting material, superconducting magnets. I. BACKGROUND ON ITER PF CONDUCTORST HE ITER Poloidal Field (PF) conductors have undergone a significant evolution in the past years. In the original ITER design (2001) the Cable-in-Conduit Conductors (CICCs) were optimized to match the current/field levels in each of the six PF coils [1]. Following recent design reviews, a number of modifications have been introduced [2], leading to the conductor designs detailed in Table I, for the envelope of operating conditions in the PF Coils reported in Table II. The main change with respect to the original design is a reduction in the Cu:nonCu ratio of the low field conductors (PF2 to PF5), implying that the Stekly condition of cryogenic stability [3] is no longer respected. Experiments on subsize conductors [4] have suggested that in the planned regime of operation, and for the expected perturbation spectrum, full cryostability (i.e. a copper fraction corresponding to the Stekly limit) is excessive. In fact, for the conditions considered, it is more convenient to design the conductor for larger temperature margin, increasing the fraction of Nb-Ti, while maintaining the copper fraction to the strict minimum demanded for protection. To achieve the operating requirements of Table II, two main conditions must be met. Firstly, the cable performance must be close to the sum of the projected performance of the individual strands, without the occurrence of the premature quenches often seen in large size Nb-Ti conductors and attributed to current non-uniformity [4], [5] (see also later discussion). In practice, we quantify this first condition using the temperature margin above the operating temperature. The design value of the temperature margin is 1.5 K, with a maximum uncertainty of 0.5 K, which results in a minimum acceptable margin of 1 K.Secondly, all AC loss sources in the cable must be controlled, so to limit the temperature increase due to the heating due to the pulsed operation. In particular, the product of the cable demagnetization factor and coupling time constant, , proportional to coupling loss, must be smalle...

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Section: The Pf Conductor Insertmentioning

confidence: 99%

Test Results From the PF Conductor Insert Coil and Implications for the ITER PF System

Bessette

Bottura

Devred

et al. 2009

IEEE Trans. Appl. Supercond.

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“…This magnet was built for testing long conductors in one layer coil configuration and generates 13 T in a bore with a radius of 0.8 m (Martovetsky, J. Minervini, A. Radovinsky et al, 2002).…”

Section: -T Magnetsmentioning

confidence: 99%

Axisymmetric Magnetic Mirror Fusion-Fission Hybrid

Moir

Martovetsky

Molvik

et al. 2011

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The achieved performance of the gas dynamic trap version of magnetic mirrors and today's technology we believe are sufficient with modest further efforts for a neutron source for material testing (Q=P fusion /P input~0 .1). The performance needed for commercial power production requires considerable further advances to achieve the necessary high Q>>10. An early application of the mirror, requiring intermediate performance and intermediate values of Q~1 are the hybrid applications. The Axisymmetric Mirror has a number of attractive features as a driver for a fusion-fission hybrid system: geometrical simplicity, inherently steady-state operation, and the presence of the natural divertors in the form of end tanks. This level of physics performance has the virtue of low risk and only modest R&D needed and its simplicity promises economy advantages. Operation at Q~1 allows for relatively low electron temperatures, in the range of 4 keV, for the DT injection energy ~ 80 keV. A simple mirror with the plasma diameter of 1 m and mirror-to-mirror length of 35 m is discussed. Simple circular superconducting coils are based on today's technology. The positive ion neutral beams are similar to existing units but designed for steady state. A brief qualitative discussion of three groups of physics issues is presented: axial heat loss, MHD stability in the axisymmetric geometry, microstability of sloshing ions.

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“…Other groups have generated solenoidal fields of 14 T in a 60 cm bore with superconducting coils; by adding resistive inserts this system reached up to 45 T 66 . The ITER Central Solenoid Model Coil has been tested to 13 T peak field, in a 1.6 m diameter bore 67 . This work, as well as that carried out earlier in the US convinces us that magnets required for DTNS are within engineering…”

Section: Vd Magnetsmentioning

confidence: 99%

The Mission and Technology of a Gas Dynamic Trap Neutron Source for Fusion Material and Component Testing and Qualification

Molvik¹,

Simonen²

2009

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Test of the ITER central solenoid model coil and CS insert

Cited by 80 publications

References 5 publications

Test Results From the PF Conductor Insert Coil and Implications for the ITER PF System

Test Results From the PF Conductor Insert Coil and Implications for the ITER PF System

Axisymmetric Magnetic Mirror Fusion-Fission Hybrid

The Mission and Technology of a Gas Dynamic Trap Neutron Source for Fusion Material and Component Testing and Qualification

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