Analysis of the transverse heat transfer coefficients in a dual channel ITER-type cable-in-conduit conductor

Marinucci, C.; Bottura, L.; Bruzzone, Pierluigi; Stepanov, B.

doi:10.1016/j.cryogenics.2007.08.008

Cited by 17 publications

(11 citation statements)

References 10 publications

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“…The bottom joint resistance and upper termination resistance were varied in the range from 0.2 to 0. 6 . The inter-triplet resistances at the joint were varied by one order of magnitude.…”

Section: B Error Due To the Difference Between Cable And Jacket Voltmentioning

confidence: 95%

“…Moreover, the temperature measurement is affected by both the sensitivity of the instruments and the non uniform temperature distribution on the conductor surface. Several studies have been devoted in the past to assess the reliability of these measurements [3]- [6]. A statistical methodology to determine the error bar in the measurement of was presented in [7].…”

Section: Introductionmentioning

confidence: 99%

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Error Estimation in the $T_{cs}$ Measurement of TF Conductors in the SULTAN Facility

Breschi

Ribani

Bessette

et al. 2012

IEEE Trans. Appl. Supercond.

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The main parameter measured in the tests of the TF conductors for the ITER machine is the current sharing temperature . In the voltmetric assessment of , the voltages are measured on the conductor jacket, due to the technical difficulties to introduce voltage taps inside the stainless steel conduit. The average voltages measured on the jacket do not exactly correspond to those that arise along the single strands, as shown by the presence of early voltages arising during the current ramp up, when the cable is still in the superconducting phase. It is therefore not trivial to evaluate the difference between the cable and jacket voltages, that gives rise to an experimental error in the measurement of . This paper reports the results of a vast simulation campaign performed with a detailed electromagnetic model of the Cable in Conduit Conductor, in which the origin and the extent of these differences have been investigated, giving an estimate for the experimental error. The impact on measurements of other sources of error such as the signal/noise ratio and the error in the temperature measurements is also reported.Index Terms-Cable in conduit conductors, error estimation, measurement.

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“…The bottom joint resistance and upper termination resistance were varied in the range from 0.2 to 0. 6 . The inter-triplet resistances at the joint were varied by one order of magnitude.…”

Section: B Error Due To the Difference Between Cable And Jacket Voltmentioning

confidence: 95%

Section: Introductionmentioning

confidence: 99%

Error Estimation in the $T_{cs}$ Measurement of TF Conductors in the SULTAN Facility

Breschi

Ribani

Bessette

et al. 2012

IEEE Trans. Appl. Supercond.

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“…Claudio Marinucci et al. [ 84 ] proposed, in 2007, an approximate analysis to obtain the mass flow rates in a bundled region to predict the friction factor coefficient and concluded the friction factor to be 0.7 times the value obtained by Katheder's [ 78 ] correlation. M. Bagnasco et al.…”

Section: Cryogenic Fluid Flow and Heat Transfer In Fusion Devicementioning

confidence: 99%

“…[ 76 ] For bundled region;

For relief hole region;

Correlation is the same as proposed by Katheder [ 78 ] for the bundled region Correlation for relief hole region with a recommended value of Coefficient N = 2 to 7 10000 < Re < 100000 (e) Claudio Marinucci et al. [ 84 ] For bundled region;

Proposed friction factor is 0.7 times the friction factor proposed by Katheder [ 78 ] 10 < Re < 1000 for bundled region (e) M. Lewandowska and M. Bagnasco [ 86 ]

Correlation has been proposed based on analogy with porous media 100 < Re < 100000 (d) (e) (g) …”

Section: Cryogenic Fluid Flow and Heat Transfer In Fusion Devicementioning

confidence: 99%

Forced flow cryogenic cooling in fusion devices: A review

Vaghela

Lakhera

Sarkar

2021

Heliyon

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The constantly increasing energy consumption along with the depleting fossil fuel resources as well as owing to the fact that the nuclear fission not being an intrinsically safe method of energy generation, it has become necessary to look for other solutions to fulfil the future energy demands. Nuclear fusion, the source of energy for billions of stars, has attracted the attention of scientists and engineers despite a lot of technical challenges in the replication of the fusion process in laboratories. For fusion to take place in a device, one of the major challenges faced is the strong magnetic confinement of the plasma using large superconducting (SC) magnets, which need efficient cryogenic cooling techniques to maintain the required low temperatures for the superconducting state. In order to maintain the compactness, the SC magnets generally employ Cable in Conduit Conductor (CICC) windings, carrying high current densities, which are cooled by the forced flow of helium at ~4 K temperature to maintain the required superconducting temperatures. The construction of CICC aims to maintain the superconductivity state by optimization of various parameters such as thermal stability, the ratio of normal conductor to SC material, mechanical strength, low hydraulic impedance, current density, magnetic field, etc. The cryogenic thermal stability of the CICC is of prime importance for safe, stable and reliable operation of SC magnets. The prediction of thermal and hydraulic behavior of the CICC in large SC magnets is difficult due to the complex geometry involved, the variation in fluid properties, various heat in-flux incidences over the long length of CICC and a complex heat transport phenomenon. Another application which utilizes a forced flow cryogenic cooling in the fusion devices is a cryo-adsorption pump for creating clean and high vacuum with large pumping speed. This paper presents an overview of the forced flow cryogenic cooling schemes in fusion devices along with a systematic review of the thermal and hydraulic studies related to CICC and cryo-adsorption pump, thereby highlighting the challenges and opportunities for further improvement in their design and performance.

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“…The agreement of empirical and calculated propagation times is fair since the parameters listed in Table 4.5 might have error bars that cumulate into such difference. However, looking at [116] and [117], v eff = 0.11 m/s is a realistic value compared with the velocities determined for different CICCs.…”

Section: A2 Minimization Of the Temperature Fluctuationmentioning

confidence: 95%

Modeling electro-magnetic and thermal Stability of Cable-in-Conduit Superconductors for Fusion Magnets

Bagni

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The views and the opinions expressed herein do not necessarily reflect those of the ITER Organization as well as EUROFusion. vi vii per mio padre to my father viii xix 5.4. JackPot Plasma Scenario short sample simulation _____________ 5.4.1. Magneto-resistance and Lorentz' force effect ___________________ 5.4.2. Simulation results ________________________________________ 5.5. Temperature evolution in a layer of CSU2 module ____________ 5.5.1. JaskPot-THEA results ______________________________________ 5.6. Conclusion ____________________________________________

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Analysis of the transverse heat transfer coefficients in a dual channel ITER-type cable-in-conduit conductor

Cited by 17 publications

References 10 publications

Error Estimation in the $T_{cs}$ Measurement of TF Conductors in the SULTAN Facility

Error Estimation in the $T_{cs}$ Measurement of TF Conductors in the SULTAN Facility

Forced flow cryogenic cooling in fusion devices: A review

Modeling electro-magnetic and thermal Stability of Cable-in-Conduit Superconductors for Fusion Magnets

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