Numerical simulation of the transient thermal-hydraulic behaviour of the ITER blanket cooling system under the draining operational procedure

Maio, P.A. Di; Dell’Orco, G.; Furmanek, A.; Garitta, S.; Merola, M.; Mitteau, R.; Raffray, R.; Spagnuolo, Gandolfo Alessandro; Vallone, E.

doi:10.1016/j.fusengdes.2015.01.024

Cited by 16 publications

(11 citation statements)

References 5 publications

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“…Blanket design involves many scientific fields. The most relevant fields include neutronics and thermal-hydraulics [2][3][4][5][6][7][8][9][10][11][12][13][14], which will directly influence the operation of the fusion reactor. In the early stage, blanket design works were performed independently without considering the coupling effects among different fields.…”

Section: Introductionmentioning

confidence: 99%

A Two-Way Neutronics/Thermal-Hydraulics Coupling Analysis Method for Fusion Blankets and Its Application to CFETR

Dai

Cao

et al. 2020

Energies

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The China Fusion Engineering Test Reactor (CFETR) is a tokamak device to validate and demonstrate fusion engineering technology. In CFETR, the breeding blanket is a vital important component that is closely related to the performance and safety of the fusion reactor. Neutronics/thermal-hydraulics (N/TH) coupling effect is significant in the numerical analysis of the fission reactor. However, in the numerical analysis of the fusion reactor, the existing coupling code system mostly adopts the one-way coupling method. The ignorance of the two-way N/TH coupling effect would lead to inaccurate results. In this paper, the MCNP/FLUENT code system is developed based on the 3D-1D-2D hybrid coupling method. The one-way and two-way N/TH coupling calculations for two typical blanket concepts, the helium-cooled solid breeder (HCSB) blanket and the water-cooled ceramic breeder (WCCB) blanket, are carried out to study the two-way N/TH coupling effect in CFETR. The numerical results show that, compared with the results from the one-way N/TH coupling calculation, the tritium breeding ration (TBR) calculated with the two-way N/TH calculation decreases by −0.11% and increases by 4.45% for the HCSB and WCCB blankets, respectively. The maximum temperature increases by 1 °C and 29 °C for the HCSB and WCCB blankets, respectively.

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Section: Introductionmentioning

confidence: 99%

A Two-Way Neutronics/Thermal-Hydraulics Coupling Analysis Method for Fusion Blankets and Its Application to CFETR

Dai

Cao

et al. 2020

Energies

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“…The research campaign has been performed following a computational approach based on the finite volume method and adopting the ANSYS CFX v.16.2 Computational Fluid-Dynamic (CFD) code, also used to evaluate hydraulic resistances for system codes [4,5,6].…”

Section: Introductionmentioning

confidence: 99%

Hydraulic analysis of EU-DEMO divertor plasma facing components cooling circuit under nominal operating scenarios

Maio

Garitta

You

et al. 2019

Fusion Engineering and Design

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Within the framework of the Work Package DIV 1-"Divertor Cassette Design and Integration" of the EUROfusion action, a research campaign has been jointly carried out by University of Palermo and ENEA to investigate the steady state thermal-hydraulic behaviour of the DEMO divertor cassette cooling circuit, focussing the attention on its Plasma Facing Components (PFCs). The research campaign has been carried out following a theoretical-computational approach based on the Finite Volume Method and adopting the commercial Computational Fluid-Dynamic code ANSYS-CFX. A realistic model of the PFCs cooling circuit has been analysed, specifically embedding each Plasma Facing Unit (PFU) cooling channel with the foreseen swirl tape turbulence promoter, hence resulting in a finite volume model much more detailed than those assessed in previous analyses. Its thermal-hydraulic performances have been numerically evaluated under nominal steady state conditions, also comparing the obtained results with the corresponding outcomes of analogous analyses carried out for a simplified PFCs configuration, without swirl tapes. Moreover, the main thermal-hydraulic parameters have been evaluated in order to check whether the considered PFCs cooling circuit might fulfil the total pressure drop requirement (p < 1.4 MPa), providing a uniform cooling of the Vertical Target PFU channels with a viable CHF margin (> 1.4). The PFCs cooling circuit thermal-hydraulic behaviour has been additionally assessed at alternative operative conditions, issued to check the viability of a coolant velocity reduction, in order to minimize corrosion and vibrations inside the PFU channels. Models, loads and boundary conditions assumed for the analyses are herewith reported and critically discussed, together with the main results obtained.

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“…A theoretical-numerical approach based on the Finite Volume Method has been followed adopting the commercial Computational Fluid-Dynamic (CFD) code ANSYS CFX v.16.2, previously used in similar studies to evaluate concentrated hydraulic resistances to be employed in system codes [6][7][8].…”

Section: Introductionmentioning

confidence: 99%

Thermal-hydraulic optimisation of the DEMO divertor cassette body cooling circuit equipped with a liner

Maio

Garitta

You

et al. 2019

Fusion Engineering and Design

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Within the framework of the Work Package DIV 1-"Divertor Cassette Design and Integration" of the EUROfusion action, a research campaign has been jointly carried out by University of Palermo and ENEA to investigate the thermal-hydraulic performances of the DEMO divertor cassette cooling system. The research activity has been focussed onto the most recent design of the Cassette Body (CB) cooling circuit equipped with a Liner, whose main function is to protect the underlying vacuum pump hole from the radiation arising from the plasma. The research campaign has been carried out following a theoretical-computational approach based on the Finite Volume Method and adopting the commercial Computational Fluid-Dynamic code ANSYS-CFX. The CB thermal-hydraulic performances have been assessed in terms of coolant and structure temperature, coolant overall pressure drop, flow velocity distribution and mass flow rate fed to the Liner cooling circuit, mainly in order to check coolant aptitude to provide a uniform and effective cooling to both CB and Liner structures. The outcomes of the study have shown some major criticalities, mainly in terms of water coolant vaporization as well as non-symmetric coolant distribution between the two Liner inlets. As a consequence, the following potential solutions have been successfully explored in order to allow the CB to safely operate while complying with its design constraints: • revising the CB design layout in order to increase the coolant mass flow rate fed to Liner; • increasing coolant inlet pressure to rise water saturation temperature and, hence, its margin against vaporization; • increasing coolant mass flow rate to reduce its overall thermal rise. The main results and the achieved optimized model are herewith described and critically discussed.

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Numerical simulation of the transient thermal-hydraulic behaviour of the ITER blanket cooling system under the draining operational procedure

Cited by 16 publications

References 5 publications

A Two-Way Neutronics/Thermal-Hydraulics Coupling Analysis Method for Fusion Blankets and Its Application to CFETR

A Two-Way Neutronics/Thermal-Hydraulics Coupling Analysis Method for Fusion Blankets and Its Application to CFETR

Hydraulic analysis of EU-DEMO divertor plasma facing components cooling circuit under nominal operating scenarios

Thermal-hydraulic optimisation of the DEMO divertor cassette body cooling circuit equipped with a liner

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