GETTHEM

The GEneral Tokamak THErmal-hydraulic Modelling (GETTHEM) code has been developed starting in 2015. It is a system-level, object-oriented, fast-running code created using Modelica, an equation-based declarative modelling language aimed at convenient modelling of complex systems. It includes models for the Primary Heat Transfer System and Balance of Plant of tokamak reactors, with both helium and water as working fluid.

Two modules are currently available: the first one is developed to enable a rapid investigation of the nominal operating transients, and, exploiting some simplifying assumptions on the thermophysical properties of the coolant, allows fast transient simulations of the entire tokamak cooling system; this module has already been successfully applied to the design verification of two Breeding Blanket concepts for the EU DEMO, namely the Helium-Cooled Pebble Bed (under development at KIT) and the Water-Cooled Lithium-Lead (under development at ENEA).

A second module is developed for the analysis of accidental conditions: in this case, as a detailed modelling of the coolant is required (to consider e.g. water flashing in a LOCA), to retain the code speed simplifying assumptions are made on geometry, in order to lump the cooling channels with similar properties and load. This module has been applied to the parametric analysis of the EU DEMO Vacuum Vessel Pressure Suppression System during the transient caused by an in-vessel LOCA.

The range of applicability of this tool is incredibly large: for instance, it may be used to optimize the flow under nominal conditions, to evaluate the global effect of localized modifications, or to rapidly explore the effect of the variation of a single parameter on an accidental transient.

Research topics

Publications

2018
  1. Parametric thermal-hydraulic analysis of the EU DEMO Water-Cooled Lithium-Lead First Wall using the GETTHEM code
    Article

    Froio, Antonio; Del Nevo, Alessandro; Martelli, Emanuela; Savoldi, Laura; Zanino, Roberto
    FUSION ENGINEERING AND DESIGN
    Elsevier
    Vol.137 pp.11 (pp.257-267) ISSN:0920-3796 DOI:10.1016/j.fusengdes.2018.10.003

  2. Modelling an in-vessel loss of coolant accident in the EU DEMO WCLL breeding blanket with the GETTHEM code
    Article

    Froio, Antonio; Bertinetti, Andrea; Ciattaglia, Sergio; Cismondi, Fabio; Savoldi, Laura; Zanino, Roberto
    FUSION ENGINEERING AND DESIGN
    Elsevier
    Vol.136 pp.5 (pp.1226-1230) ISSN:0920-3796 DOI:10.1016/j.fusengdes.2018.04.106

  3. Multi-scale thermal-hydraulic modelling for the Primary Heat Transfer System of a tokamak
    Doctoral thesis

    Froio, Antonio
    Politecnico di Torino
    pp.167 DOI:10.6092/polito/porto/2704378

  4. Thermal-Hydraulic Analysis of the EU DEMO Helium-Cooled Pebble Bed Breeding Blanket Using the GETTHEM Code
    Article

    Froio, Antonio; Cismondi, Fabio; Savoldi, Laura; Zanino, Roberto
    IEEE TRANSACTIONS ON PLASMA SCIENCE
    IEEE
    Vol.46 pp.10 (pp.1436-1445) ISSN:0093-3813 DOI:10.1109/TPS.2018.2791678

2017
  1. Dynamic thermal-hydraulic modelling of the EU DEMO WCLL breeding blanket cooling loops
    Article

    Froio, Antonio; Casella, F.; Cismondi, F.; Del Nevo, A.; Savoldi, Laura; Zanino, Roberto
    FUSION ENGINEERING AND DESIGN
    Elsevier Ltd
    Vol.124 pp.5 (pp.887-891) ISSN:0920-3796 DOI:10.1016/j.fusengdes.2017.01.062

2016
  1. Dynamic thermal-hydraulic modelling of the EU DEMO HCPB breeding blanket cooling loops
    Article

    Froio, Antonio; Bachmann, C.; Cismondi, F.; Savoldi, Laura; Zanino, Roberto
    PROGRESS IN NUCLEAR ENERGY
    Elsevier Ltd
    Vol.93 pp.17 (pp.116-132) ISSN:0149-1970 DOI:10.1016/j.pnucene.2016.08.007

Total: 6

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