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Träfflista för sökning "WFRF:(Casiraghi C) srt2:(2020-2024)"

Sökning: WFRF:(Casiraghi C) > (2020-2024)

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  • Glasbey, JC, et al. (författare)
  • 2021
  • swepub:Mat__t
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  • Murari, A., et al. (författare)
  • A control oriented strategy of disruption prediction to avoid the configuration collapse of tokamak reactors
  • 2024
  • Ingår i: Nature Communications. - 2041-1723 .- 2041-1723. ; 15:1
  • Tidskriftsartikel (refereegranskat)abstract
    • The objective of thermonuclear fusion consists of producing electricity from the coalescence of light nuclei in high temperature plasmas. The most promising route to fusion envisages the confinement of such plasmas with magnetic fields, whose most studied configuration is the tokamak. Disruptions are catastrophic collapses affecting all tokamak devices and one of the main potential showstoppers on the route to a commercial reactor. In this work we report how, deploying innovative analysis methods on thousands of JET experiments covering the isotopic compositions from hydrogen to full tritium and including the major D-T campaign, the nature of the various forms of collapse is investigated in all phases of the discharges. An original approach to proximity detection has been developed, which allows determining both the probability of and the time interval remaining before an incoming disruption, with adaptive, from scratch, real time compatible techniques. The results indicate that physics based prediction and control tools can be developed, to deploy realistic strategies of disruption avoidance and prevention, meeting the requirements of the next generation of devices.
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  • Balbinot, L., et al. (författare)
  • Multi-code estimation of DTT edge transport parameters
  • 2023
  • Ingår i: Nuclear Materials and Energy. - : Elsevier BV. - 2352-1791. ; 34
  • Tidskriftsartikel (refereegranskat)abstract
    • The main goal of the Divertor Tokamak Test facility (DTT) is to operate with a high value of power-exhaust-relevant parameter Psoz/R in plasma scenarios similar to those foreseen for the Demonstration Fusion Power Plant (DEMO) in terms of low collisionality and neutral opacity. For these unique characteristics, accurate modelling of the principal scenario is necessary for machine designing. In edge numerical codes, cross-field transport profiles have a high impact on modelling results. This work aims at providing a coherent set of transport parameters for DTT full-power (FP) single-null (SN) scenario edge modelling. To evaluate such parameters for DTT, a transport analysis on the current machine has been performed using SOLEDGE2D-EIRENE and SOLPS-ITER. The transport parameters to be used in the simulations of the DTT single-null scenario were selected using two complementary methods. The first is the modelling of JET and Alcator C-Mod (C-Mod) with SOLEDGE2D-EIRENE and SOLPS-ITER, validating transport parameters by comparing modelling results to experimental data from pulses which are considered DTT-relevant. JET pulses were selected with the highest auxiliary input power (from 29 to 33 MW), plasma current and toroidal field to better match DTT parameters; nitrogen and neon seeded pulses were selected to check possible seeding material dependencies. The considered C-Mod pulse better matches DTT plasma density and neutral opacity. Transport parameters are then scaled to DTT according to scaling laws. The second method derives the transport parameters by tuning their values inside the DTT separatrix to reproduce the pedestal profiles predicted by the EPED model via the Europed code and applied in DTT. The derived set of DTT transport parameters is consistent with the results obtained by modelling present machines, reproduces the expected heat flux decay length in detached conditions and, inside the separatrix, reproduces the predicted pedestal using transport parameters which are coherent with what is predicted by the quasi-linear turbulent model QuaLiKiz.
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  • Mantica, P., et al. (författare)
  • Detection of alpha heating in JET-ILW DT plasmas by a study of the electron temperature response to ICRH modulation
  • 2024
  • Ingår i: Nuclear Fusion. - Culham Sci Ctr, JET, EUROfus Consortium, Abingdon OX14 3DB, England. [Mantica, P.; Casiraghi, I.; Dal Molin, A.; Rigamonti, D.; Tardocchi, M.] CNR, Inst Plasma Sci & Technol, Milan, Italy. [Auriemma, F.] Consorzio RFX ISTP CNR, Padua, Italy. [Gallart, D.; Mantsinen, M.] Barcelona Supercomp Ctr, Barcelona, Spain. [Kirov, K.; Jacquet, P.; Kiptily, V.; Litherland-Smith, E.; Maggi, C. F.; Maslov, M.; Menmuir, S.; Stancar, Z.; Sun, H.; Szepesi, G.] Culham Sci Ctr, UKAEA, Abingdon, England. [Lerche, E.; Van Eester, D.] ERM KMS, Lab Plasma Phys, Brussels, Belgium. [Salmi, A.] VTT, POB 1000, FI-02044 Espoo, Finland. [Delabie, E.] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA. [Eriksson, J.] Uppsala Univ, Dept Phys & Astron, Uppsala, Sweden. [Garcia, J.; Huynh, P.] CEA, IRFM, St Paul Les Durance, France. [$$$Jonsson, T.] KTH, Fus Plasma Phys, EES, Stockholm, Sweden. [Mantsinen, M.] ICREA, Barcelona, Spain. [Marcer, G.; Nocente, M.] Univ Milano Bicocca, Milan, Italy. [Peluso, E.] Univ Roma Tor Vergata, Rome, Italy. [Peluso, E.; Pucella, G.] ENEA CR Frascati, Frascati, Italy. : IOP Publishing. - 0029-5515 .- 1741-4326. ; 64:8
  • Tidskriftsartikel (refereegranskat)abstract
    • In the JET DTE2 campaign a new method was successfully tested to detect the heating of bulk electrons by alpha-particles, using the dynamic response of the electron temperature T e to the modulation of ion cyclotron resonance heating (ICRH). A fundamental deuterium (D) ICRH scheme was applied to a tritium-rich hybrid plasma with D-neutral beam injection (NBI). The modulation of the ion temperature T i and of the ICRH accelerated deuterons leads to modulated alpha-heating with a large delay with respect to other modulated electron heating terms. A significant phase delay of similar to 40 degrees is measured between central T e and T i, which can only be explained by alpha-particle heating. Integrated modelling using different models for ICRH absorption and ICRH/NBI interaction reproduces the effect qualitatively. Best agreement with experiment is obtained with the European Transport Solver/Heating and Current Drive workflow.
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  • Resultat 1-13 av 13

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