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48 results on '"Savoldi Richard, L."'

9. CtFD analysis of HTS current lead fin-type heat exchanger for fusion applications

Author

Savoldi Richard, L., Class, A., Fietz, W.H., Heller, R., Rizzo, E., and Zanino, R.

Subjects
Fluid dynamics -- Analysis, Fusion reactors -- Design and construction, Heat exchangers -- Design and construction, High temperature superconductors -- Usage, Business, Electronics, Electronics and electrical industries
Published
2010

10. Analysis of quench propagation in the ITER poloidal field conductor insert (PFCI)

Author

Zanino, R., Bonifetto, R., and Savoldi Richard, L.

Subjects
Niobium -- Magnetic properties, Niobium -- Electric properties, Nuclear reactors -- Design and construction, Superconducting magnets -- Testing, Technical institutes -- Management, Titanium alloys -- Magnetic properties, Titanium alloys -- Electric properties, Company business management, Business, Electronics, Electronics and electrical industries, International Thermonuclear Experimental Reactor -- Management
Published
2010

11. Evaluation of the current sharing temperature of the ITER Toroidal Field Model Coil

Author

Heller, R., Ciazynski, D., Duchateau, J.L., Marchese, V., Zanino, R., and Savoldi-Richard, L.

Subjects
Superconducting magnets -- Research, Fusion reactors -- Research, Business, Electronics, Electronics and electrical industries
Abstract

Models for evaluation of the current sharing temperature of the International Thermonuclear Experimental Reactor (ITER) Toroidal Field Model Coil are described and discussed.

Published
2003

13. The ITER toroidal field model coil project

Author

Ulbricht, A., Duchateau, J.L., Fietz, W.H., Ciazynski, D., Fillunger, H., Fink, S., Heller, R., Maix, R., Nicollet, S., Raff, S., Ricci, M., Salpietro, E., Zahn, G., Zanino, R., Bagnasco, M., Besette, D., Bobrov, E., Bonicelli, T., Bruzzone, P., Darweschsad, M.S., Decool, P., Dolgetta, N., della Corte, A., Formisano, A., Grünhagen, A., Hertout, P., Herz, W., Huguet, M., Hurd, F., Ilyin, Yu., Komarek, P., Libeyre, P., Marchese, V., Marinucci, C., Martinez, A., Martone, R., Martovetsky, N., Michael, P., Mitchell, N., Nijhuis, A., Nöther, G., Nunoya, Y., Polak, M., Portone, A., Savoldi Richard, L., Spadoni, M., Süßer, M., Turtú, S., Vostner, A., Takahashi, Y., Wüchner, F., and Zani, L.

Published
2005
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20. Preparation of the ITER Poloidal Field Conductor Insert (PFCI) Test

Author

Zanino, R., Egorov, S., Kim, K., Martovetsky, N., Nunoya, Y., Okuno, K., Salpietro, E., Sborchia, C., Takahashi, Y., Weng, P., Bagnasco, M., Savoldi Richard, L., Polak, M., Formisano, A., Zapretilina, E., Shikov, A., Vedernikov, G., Ciazynski, D., Zani, L., Muzzi, L., Della Corte, A., Sugimoto, M., Hamada, K., Portone, A., Hurd, F., Mitchell, N., Nijhuis, Arend, and Ilyin, Y.

Subjects
METIS-225241
Published
2005

22. THELMA status

Author

Bellina, F., Boso, Daniela, Ribani, P. L., Savoldi Richard, L., and Zanino, R.

Published
2004

23. Tcs Tests and Performance Assessment of the ITER Toroidal Field Model Coil (Phase II)

Author

Zanino, R., Bagnasco, M., Dittrich, G., Fietz, W., Fillunger, H., Hampshire, D., Heller, H., Komarek, P., Langhans, O., Maix, R., Marchese, V., Martovetsky, N., Mitchell, N., Nijhuis, Arend, Raff, S., Ricci, M.V., Suesser, M., Salpietro, E., Savoldi Richard, L., Taylor, D.M.J., Ulbricht, A., Vostner, A., Wuechner, F., and Zahn, G.

Subjects
METIS-223094
Published
2004

34. Test Results of Two European ITER TF Conductor Samples in SULTAN

Author

Bruzzone, P., primary, Bagnasco, M., additional, Calvi, M., additional, Cau, F., additional, Ciazynski, D., additional, della Corte, A., additional, Di Zenobio, A., additional, Muzzi, L., additional, Nijhuis, A., additional, Salpietro, E., additional, Savoldi Richard, L., additional, Turtu, S., additional, Vostner, A., additional, Wesche, R., additional, and Zanino, R., additional

Published
2008
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35. STABILITY ANALYSIS OF THE ITER TF CONDUCTOR

Author

Savoldi Richard, L., primary, Zanino, R., additional, Weisend, J. G., additional, Barclay, John, additional, Breon, Susan, additional, Demko, Jonathan, additional, DiPirro, Michael, additional, Kelley, J. Patrick, additional, Kittel, Peter, additional, Klebaner, Arkadiy, additional, Zeller, Al, additional, Zagarola, Mark, additional, Van Sciver, Steven, additional, Rowe, Andrew, additional, Pfotenhauer, John, additional, Peterson, Tom, additional, and Lock, Jennifer, additional

Published
2008
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36. Predictive Analysis of the ITER Poloidal Field Conductor Insert (PFCI) Test Program

Author

Zanino, R., primary, Astrov, M., additional, Bagnasco, M., additional, Baker, W., additional, Bellina, F., additional, Ciazynski, D., additional, Egorov, S., additional, Kim, K., additional, Kvitkovic, J.L., additional, Lacroix, B., additional, Martovetsky, N., additional, Mitchell, N., additional, Muzzi, L., additional, Nunoya, Y., additional, Okuno, K., additional, Polak, M., additional, Ribani, P.L., additional, Salpietro, E., additional, Savoldi Richard, L., additional, Sborchia, C., additional, Takahashi, Y., additional, Weng, P., additional, Wesche, R., additional, Zani, L., additional, and Zapretilina, E., additional

Published
2007
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37. Analysis of Thermal-Hydraulic Gravity/ Buoyancy Effects in the Testing of the ITER Poloidal Field Full Size Joint Sample (PF-FSJS).

Author

Zanino, R., Bruzzone, P., Ciazynski, D., Ciotti, M., Gislon, P., Nicollet, S., and Savoldi Richard, L.

Subjects
AQUEDUCTS, HYDRAULIC structures, MAGNETIC fields, FIELD coils in electric generators, HELIUM, COOLING
Abstract

The PF-FSJS is a full-size joint sample, based on the NbTi dual-channel cable-in-conduit conductor (CICC) design currently foreseen for the International Thermonuclear Experimental Reactor (ITER) Poloidal Field coil system. It was tested during the summer of 2002 in the Sultan facility of CRPP at a background peak magnetic field of typically 6 T. It includes about 3 m of two jointed conductor sections, using different strands but with identical layout. The sample was cooled by supercritical helium at nominal 4.5–5.0 K and 0.9–1.0 MPa, in forced convection from the top to the bottom of the vertical configuration. A pulsed coil was used to test AC losses in the two legs resulting, above a certain input power threshold, in bundle helium backflow from the heated region. Here we study the thermal-hydraulics of the phenomenon with the M&M code, with particular emphasis on the effects of buoyancy on the helium dynamics, as well as on the thermal-hydraulic coupling between the wrapped bundles of strands in the annular cable region and the central cooling channel. Both issues are ITER relevant, as they affect the more general question of the heat removal capability of the helium in this type of conductors. © 2004 American Institute of Physics [ABSTRACT FROM AUTHOR]

Published
2004
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38. Thermal-Hydraulic Issues in the ITER Toroidal Field Model Coil (TFMC) Test and Analysis.

Author

Zaninoa, R., Bagnascoa, M., Fillunger, H., Hellerc, R., Savoldi Richard, L., Suesserc, M., and Zahnc, G.

Subjects
ELECTRIC reactors, MAGNETIC fields, ELECTRIC coils, HELIUM, ELECTRICAL conductors
Abstract

The International Thermonuclear Experimental Reactor (ITER) Toroidal Field Model Coil (TFMC) was tested in the Toska facility of Forschungszentrum Karlsruhe during 2001 (standalone) and 2002 (in the background magnetic field of the LCT coil). The TFMC is a racetrack coil wound in five double pancakes on stainless steel radial plates using Nb3Sn dual-channel cable-in-conduit conductor (CICC) with a thin circular SS jacket. The coil was cooled by supercritical helium in forced convection at nominal 4.5 K and 0.5 MPa. Instrumentation, all outside the coil, included voltage taps, pressure and temperature sensors, as well as flow meters. Additionally, differential pressure drop measurement was available on the two pancakes DP1.1 and DP1.2, equipped with heaters. Two major thermal-hydraulic issues in the TFMC tests will be addressed here: 1) the pressure drop along heated pancakes and the comparison with friction factor correlations; 2) the quench initiation and propagation. Other thermal-hydraulic issues like heat generation and exchange in joints, radial plates, coil case, or the effects of the resistive heaters on the helium dynamics, have been already addressed elsewhere. © 2004 American Institute of Physics [ABSTRACT FROM AUTHOR]

Published
2004
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39. Effects of Mass Flow Rate Imbalance Among Petals During TCS Measurements of ITER TF Short Samples in SULTAN.

Author

Savoldi Richard, L., Bellina, F., Breschi, M., Ribani, P. L., Subba, F., and Zanino, R.

Subjects
*TOROIDAL harmonics, *ELECTRICAL conductors, *SOLDER & soldering, *HELIUM, *ELECTRIC cables, *WRAPPING materials, *FUSION reactors, *SIMULATION methods & models
Abstract

Since year 2009, the joint of the toroidal field (TF) conductor samples tested in the SULTAN facility at PSI Villigen, CH, is solder-filled, so that the helium coolant can only flow axially inside the central channel. The latter is however plugged starting \sim40–45 mm downstream of the joint. The helium has then to pass from the central channel into the annular cable region over such a short length that the desired homogeneity of the flow distribution among the petals in the high field region is not guaranteed a priori, since central helix and petal wrappings act as azimuthally non-uniform obstacles to the radial flow. In the paper we first present a geometrical model for estimating this interference to the radial flow, and combine it with a CFD (ANSYS-FLUENT) model of the hydraulic effect of the plug, in order to estimate the mass flow rate imbalance among the petals at the beginning of the plug. This is then used as boundary condition by the THELMA code, to parametrically assess the results of a TCS measurement. [ABSTRACT FROM AUTHOR]

Published
2011
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40. THELMA code electromagnetic model of ITER superconducting cables and application to the ENEA stability experiment

Author

Ciotti, M, Nijhuis, A, Ribani, P L, Savoldi Richard, L, and Zanino, R

Abstract

The new THELMA code, including a thermal-hydraulic (TH) and an electro-magnetic (EM) model of a cable-in-conduit conductor (CICC), has been developed. The TH model is at this stage relatively conventional, with two fluid components (He flowing in the annular cable region and He flowing in the central channel) being particular to the CICC of the International Thermonuclear Experimental Reactor (ITER), and two solid components (superconducting strands and jacket/conduit). In contrast, the EM model is novel and will be presented here in full detail. The results obtained from this first version of the code are compared with experimental results from pulsed tests of the ENEA stability experiment (ESE), showing good agreement between computed and measured deposited energy and subsequent temperature increase.

Published
2006
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41. Coupled mechanical-electromagnetic-thermal-hydraulic effects in Nb3Sn cable-in-conduit conductors for ITER

Author

Zanino, R, Ciazynski, D, Mitchell, N, and Savoldi Richard, L

Abstract

The crucial multi-physics problem of how to extrapolate from the performance of an isolated Nb3Sn strand measured in the laboratory to the performance of a superconducting coil using multi-strand twisted cables is addressed here. We consider the particular case of the path going from the LMI strand to the international thermonuclear experimental reactor (ITER) toroidal field model coil (TFMC), through its associated Full Size Joint Sample, the TFMC-FSJS. Mechanical, electromagnetic and thermal-hydraulic conditions are simulated using the ANSYS, ENSIC and Mithrandir/M&M codes, respectively. At least in this case, the DC performance of the short sample turns out to be relatively close to (considering error bars) but not fully representative of that of the coil, showing higher (less compressive) effective thermal strain but also higher sensitivity to the electromechanical load.

Published
2005
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48. Preparation of the ITER Poloidal Field Conductor Insert (PFCI) Test

Author

Alessandro Formisano, Masayoshi Sugimoto, Daniel Ciazynski, Nicolai Martovetsky, N. Mitchell, Y. Takahashi, P. Weng, G. Vedernikov, Roberto Zanino, Kiyoshi Okuno, Keeman Kim, M. Polak, E. Zapretilina, Ettore Salpietro, Arend Nijhuis, L. Zani, A. K. Shikov, C. Sborchia, Yu.A. Ilyin, Alfredo Portone, F. Hurd, M. Bagnasco, L.S. Richard, A. della Corte, M. Ricci, K. Hamada, S. Egorov, Luigi Muzzi, Yoshihiko Nunoya, Formisano, Alessandro, Martone, Raffaele, Zanino, R., Kim, K., Egorov, S., Martovetsky, N., Nunoya, Y., Okuno, K., Salpietro, E., Takahashi, Y., Sborchia, C., Weng, P., SAVOLDI RICHARD, L., Bagnasco, M., Zapretilina, E., Polak, M., Shikov, A., Vedernikov, G., Ciazynski, D., Zani, L., Muzzi, L., Ricci, M., and DELLA CORTE, A.

Subjects
Resistive touchscreen, Materials science, Thermonuclear fusion, Nuclear Fusion, Heating element, Instrumentation, Nuclear engineering, Solenoid, METIS-223396, Condensed Matter Physics, Electronic, Optical and Magnetic Materials, Conductor, Cavi CICC, Nuclear magnetic resonance, Electromagnetic coil, ITER, Electrical and Electronic Engineering, Voltage
Abstract

The Poloidal Field Conductor Insert (PFCI) of the International Thermonuclear Experimental Reactor (ITER) has been designed in the EU and is being manufactured at Tesla Engineering, UK, in the frame of a Task Agreement with the ITER International Team. Completion of the PFCI is expected at the beginning of 2005. Then, the coil shall be shipped to JAERI Naka, Japan, and inserted into the bore of the ITER Central Solenoid Model Coil, where it should be tested in 2005 to 2006. The PFCI consists of a NbTi dual-channel conductor, almost identical to the ITER PF1 and PF6 design, 45 m long, with a 50 mm thick square stainless steel jacket, wound in a single-layer solenoid. It should carry up to 50 kA in a field of 6 T, and it will be cooled by supercritical He at 4.5 K and 0.6 MPa. An intermediate joint, representative of the ITER PF joints and located at relatively high field, will be an important new item in the test configuration with respect to the previous ITER Insert Coils. The PFCI will be fully instrumented with inductive and resistive heaters, as well as with voltage taps, Hall probes, pick-up coils, temperature sensors, pressure gauges, strain and displacement sensors. The test program will be aimed at DC and pulsed performance assessment of conductor and intermediate joint, AC loss measurement, stability and quench propagation, thermal-hydraulic characterization. Here we give an overview of the preparatory work toward the test, including a review of the coil manufacturing and of the available instrumentation, a discussion of the most likely test program items, and a presentation of the supporting modeling and characterization work performed so far.

Published
2005

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