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-
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 -
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 -
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 -
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
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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
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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