“…The 4C code has also been validated against the experimental data of W7-X for the cool-down from room temperature to the SC transition temperature ~10K [ 43 ]. The thermo-hydraulic validation of the code has also done for the 25kA safety discharge of the TFMC [ 44 ]. The 4C code has been rigorously validated for various SC magnet system [ 43 , 44 , 45 , 46 , 47 , 48 , 49 ] including even predictive validation where the simulations are performed before/without the knowledge of the results of the measurements [ 50 ].…”
Section: Cryogenic Fluid Flow and Heat Transfer In Fusion Devicementioning
confidence: 99%
“…There have been several improvements in the design and construction of CICC since it was first proposed by Hoenig and Montgomery in 1970s [ 72 ]. The typical cross-sections of such Cable in Conduit Conductor (CICC) are shown in Figure 8 in which Type (a) CICC used in SST-1 [ 73 ], Type (b) CICC used for W7-X [ 74 ], Type (e) CICC used for ITER PF and CS conductor samples [ 75 , 76 ], Type (g) CICC used for TF conductor sample for the ITER project [ 77 ] and Type (h) CICC is ENEA conductor envisaged for the EU DEMO [ 44 ]. Figure 8 Various typical cross-sections of CICC [(a) square jacket without relief hole (b) internally round jacket without relief hole (c) round jacket without relief hole (d) square jacket with relief hole (e) internally round jacket with relief hole (g) round jacket with relief hole (h) rectangular jacket with two relief holes].…”
Section: Cryogenic Fluid Flow and Heat Transfer In Fusion Devicementioning
confidence: 99%
“…Dedicated thermo-hydraulic tests were carried out for Type-(h) CICC on a full scale, short length CICC sample having a rectangular cross-section with two small pressure relief ‘holes’ of 5 mm diameter [ 44 ]. The CICC consisted of Nb 3 Sn strands with copper as a stabilizer for TF magnet cooled by SHe.…”
Section: Cryogenic Fluid Flow and Heat Transfer In Fusion Devicementioning
confidence: 99%
“…The thermo-hydraulic validation of the code has also done for the 25kA safety discharge of the TFMC [44]. The 4C code has been rigorously validated for various SC magnet system [43,44,45,46,47,48,49] including even predictive validation where the simulations are performed before/without the knowledge of the results of the measurements [50]. The rigorous validation activity carried out on 4C code puts it in a different perspective with respect to the others.…”
Section: Cryogenic Fluid Flow and Heat Transfer In Fusion Devicementioning
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.
“…The 4C code has also been validated against the experimental data of W7-X for the cool-down from room temperature to the SC transition temperature ~10K [ 43 ]. The thermo-hydraulic validation of the code has also done for the 25kA safety discharge of the TFMC [ 44 ]. The 4C code has been rigorously validated for various SC magnet system [ 43 , 44 , 45 , 46 , 47 , 48 , 49 ] including even predictive validation where the simulations are performed before/without the knowledge of the results of the measurements [ 50 ].…”
Section: Cryogenic Fluid Flow and Heat Transfer In Fusion Devicementioning
confidence: 99%
“…There have been several improvements in the design and construction of CICC since it was first proposed by Hoenig and Montgomery in 1970s [ 72 ]. The typical cross-sections of such Cable in Conduit Conductor (CICC) are shown in Figure 8 in which Type (a) CICC used in SST-1 [ 73 ], Type (b) CICC used for W7-X [ 74 ], Type (e) CICC used for ITER PF and CS conductor samples [ 75 , 76 ], Type (g) CICC used for TF conductor sample for the ITER project [ 77 ] and Type (h) CICC is ENEA conductor envisaged for the EU DEMO [ 44 ]. Figure 8 Various typical cross-sections of CICC [(a) square jacket without relief hole (b) internally round jacket without relief hole (c) round jacket without relief hole (d) square jacket with relief hole (e) internally round jacket with relief hole (g) round jacket with relief hole (h) rectangular jacket with two relief holes].…”
Section: Cryogenic Fluid Flow and Heat Transfer In Fusion Devicementioning
confidence: 99%
“…Dedicated thermo-hydraulic tests were carried out for Type-(h) CICC on a full scale, short length CICC sample having a rectangular cross-section with two small pressure relief ‘holes’ of 5 mm diameter [ 44 ]. The CICC consisted of Nb 3 Sn strands with copper as a stabilizer for TF magnet cooled by SHe.…”
Section: Cryogenic Fluid Flow and Heat Transfer In Fusion Devicementioning
confidence: 99%
“…The thermo-hydraulic validation of the code has also done for the 25kA safety discharge of the TFMC [44]. The 4C code has been rigorously validated for various SC magnet system [43,44,45,46,47,48,49] including even predictive validation where the simulations are performed before/without the knowledge of the results of the measurements [50]. The rigorous validation activity carried out on 4C code puts it in a different perspective with respect to the others.…”
Section: Cryogenic Fluid Flow and Heat Transfer In Fusion Devicementioning
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.
“…Moreover, the model accounts for both Joule heating from eddy currents in the casing, and AC losses in the cable induced by the fast discharge triggered by the quench protection system. Friction factor correlations and heat transfer values used in the model are validated on experimental tests [18]. The nominal DEMO pulsed scenario [19] is assumed for simulations.…”
In the framework of the DEMOnstration fusion power plant (DEMO) design coordinated by the EUROfusion consortium, a pre-conceptual design of the superconducting magnet system has been developed. For the toroidal field coils (TFCs), three winding pack (WP) options have been proposed; exploring different winding approaches (pancakes vs. layers), and manufacturing techniques (react & wind vs. wind & react Nb 3 Sn). Thermal-hydraulic and mechanical analyses on the three WPs have produced encouraging results, with some critical issues to be solved in future studies and optimizations. The experimental tests on TF prototype short sample conductors have demonstrated a limited performance degradation with electromagnetic cycles and significantly lower effective strains than most of the large-size Nb 3 Sn conductors reported in literature. The toroidal field quench protection circuit has been studied, starting from different topologies and focusing on the most promising one. Two designs are also presented for the central solenoid magnet, with preliminary evaluations on the AC losses during the plasma breakdown. Finally, the design of a TF winding pack based on HTS conductors and the experimental tests on "fusion-relevant" HTS cables are illustrated.
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