Dual channel cable in conduit thermohydraulics: Influence of some design parameters

Nicollet, S.; Duchateau, J.L.; Fillunger, H.; Martinez, A.; Parodi, S.

doi:10.1109/77.828425

Cited by 41 publications

(10 citation statements)

References 2 publications

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“…A first assessment of this conductor pressure drop was done according (1) and using Nicollet formulae [2] for friction factor f determination versus void fraction V f and Reynolds value (2) at the reference flow rate operating point Q m of 4g/s at 0.5 MPa, 4.5 K.…”

Section: Conductor Characterisationmentioning

confidence: 99%

Detailed design studies at CEA for JT-60SA TF coils

Decool

Maréchal

Portafaix

et al. 2011

Fusion Engineering and Design

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Section: Conductor Characterisationmentioning

confidence: 99%

Detailed design studies at CEA for JT-60SA TF coils

Decool

Maréchal

Portafaix

et al. 2011

Fusion Engineering and Design

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“…Later work based on pressure drop vs. mass flow rate data in the QUELL CICC [10] central channel, under the assumption of validity of [3] for f B , verified good agreement using a ffl = 2.5 [11] (although the definition of DH H and A H was not specified). However, it soon became apparent that details in the spiral geometry (e.g., its shapecircular vs. flat, or the size g of the gap left open between bundle and hole) could have significant influence on the pressure drop, and cannot be condensed in a single multiplier of the smooth pipe friction factor [8], [12]. Tests of spiral rib-roughened pipes using N2 were performed for three spirals with different gaps in the range 2.4 mm to 5.3 mm with the same ID/OD, including the Showa spiral of Table 1, which should be the same spiral as used in both CSMC and TFMC 4 .…”

Section: Friction In the Central Channel -Smoothmentioning

confidence: 99%

“…Tests of spiral rib-roughened pipes using N2 were performed for three spirals with different gaps in the range 2.4 mm to 5.3 mm with the same ID/OD, including the Showa spiral of Table 1, which should be the same spiral as used in both CSMC and TFMC 4 . This database gave rise to least square fits for each spiral [8], which have been adopted in the present ITER DC, and furthermore to a general correlation, valid for all three spirals, of the form f H = f H (Re H , g/h) [13], where h is the spiral thickness (= 1 mm for all present ITER CICO). For the Showa spiral the ITER DC give f H = 0.3024 Re H "°' 0707 (2)…”

Section: Friction In the Central Channel -Smoothmentioning

confidence: 99%

A Critical Assessment of Pressure Drop Design Criteria for the Conductors of the ITER Magnets

Zanino¹,

Bruzzone²,

Savoldi³

2006

AIP Conference Proceedings

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The available database for the friction factors to be used in the annular cable and in the central channel regions of cable-in-conduit conductors (CICC) for the superconducting magnets of the International Thermonuclear Experimental Reactor (ITER) is reviewed here for the first time. There is particular reference to its internal consistency as well as the correlations presently used in the ITER design criteria. Limitations and issues in the present status are emphasized and recommendations for improvements are given.

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“…For the friction factors in the cable region and central channel the correlations reported in [9] have been used, as presently recommended by ITER IO. Revised correlations have been recently proposed, see [10], but not yet adopted.…”

Section: Other Input Assumptionsmentioning

confidence: 99%

Stability Analysis of the Iter Cs Coil Conductors

Savoldi¹,

Bessette²,

Zanino³

et al. 2010

AIP Conference Proceedings

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The stability analysis of the International Thermonuclear Experimental Reactor (ITER) Central Solenoid (CS) coil Nb3Sn conductor is performed following a similar approach to that recently used for the ITER Toroidal Field and Poloidal Field conductors. The most critical conductors in the winding pack, as well as the most critical (minimum temperature margin) location along them, are identified by the application of the Vincenta code, which also provides the initial and boundary conditions in the reference case. The Mithrandir code is then applied to these conductors, using a much finer grid than affordable in the Vincenta analysis, in order to capture the details of normal zone initiation and possible recovery to SC state when different square wave disturbances of length L in the range [0.01 m, 7 m] and duration τ in the range [1 ms, 100 ms] are applied to the superconducting cable. The computed minimum quench energy is shown to be typically above (in one case borderline to) the expected disturbance. The sensitivity to parametric variations of the heat transfer coefficient between strands and helium is significant for some disturbances. The inclusion of an external circuit in the model, providing selfconsistent boundary conditions, does not influence the results.

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Dual channel cable in conduit thermohydraulics: Influence of some design parameters

Cited by 41 publications

References 2 publications

Detailed design studies at CEA for JT-60SA TF coils

Detailed design studies at CEA for JT-60SA TF coils

A Critical Assessment of Pressure Drop Design Criteria for the Conductors of the ITER Magnets

Stability Analysis of the Iter Cs Coil Conductors

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