Closed projects

Nuclear fission related projects

• H2020 Euratom Research Programme:
  • SAMOFAR - Safety Assessment of the Molten Salt Fast Reactor (Aug 2015 – Jul 2019)
• VII European Framework Programme:
  • LEADER - Lead-cooled European Advanced Demonstration Reactor (Apr 2010 - Oct 2013)
  • ECNET - EU-China Nuclear Education and Training Cooperation (Mar 2011 - Feb 2013)
  • EVOL - Evaluation and Viability of Liquid Fuel Fast Reactor Systems (Dec 2010 - Nov 2013)
  • FREYA - Fast Reactor Experiments for hYbrid Applications (Mar 2011 - Feb 2016)
• VI European Framework Programme:
  • EUROTRANS - European research Programme for the transmutation of high level nuclear waste in an accelerator driven system (Apr 2005 - March 2010)
  • ALISIA - Assessment of LIquid Salts for innovative applications (Jan 2007 - March 2008)
  • EU-Asia-Link Programme: An EU-China Campus for Energy & Environment

Nuclear fusion related projects

• H2020 Euratom Research Programme: Linked Third Party of ENEA, member of the EUROfusion Consortium
  • Work Package BB - Breeding Blanket:
    • Contribution to Design Engineering for WCLL – 2019 activities
    • Contribution to Design Engineering for WCLL – 2018 activities
    • Preliminary engineering Design of PAV TES for HCLL/WCLL BB with welding procedure, stress mechanical analyss, thermofluid dynamic evaluation
    • DDD of the WCLL TES
    • Design of a scaled down mock-up of a BSS segment for the WCLL BB
    • Sizing of BSS mock-ups for the HELOKA test facility – 2017 activities
    • Design of mock-ups for test facility – 2016 activities
  • Work Package MAG - Magnet system:
    • Support to the thermal-hydraulic design and analysis of the DEMO magnet system
    • 4C code validation and DEMO magnet system reliability-based design
    • Support to the thermal-hydraulic design and analysis of the DEMO TF coils with the WP#2 design
    • Support to the thermal-hydraulic characterization of the ENEA W&R Prototype Conductor and WP
    • Assess thermal-hydraulic properties of WP#2 with 4C & code comparison
    • Sizing and preliminary design of feeders
    • RAMI analysis of the DEMO magnet system
  • Work Package PMI - Plant Level System Engineering, Design Integration and Physics Integration:
    • Global thermohydraulic model and support of thermohydraulic assessments
    • Thermohydraulic analysis of the blanket primary cooling loop
    • Thermohydraulic analysis of the HCPB blanket primary cooling loop
    • SOLPS Calculations for DEMO
    • Prediction of wall loads during disruptions in DEMO
    • Thermal analysis of PFC during runaways electrons (REs)
    • Design and analysis of the VVPSS tank and connection to the VV incl. upper port
    • Analysis of VVPSS for Helium and Water cooled Breeding Blankets
  • Work Package DTT1 - Assessment of alternative divertor geometries and liquid metals PFCs
    • Contribution to Design of a next generation European Edge and Boundary Code for reactor relevant devices with various magnetic configurations (including coupling to turbulence codes and pedestal-SOL interface)
    • Impurity Control
    • Safety Analyses
• Support to the identification of synergies and gaps in the modelling of a Molten Salt Blanket for the ARC reactor (with ENI, October 2019 - March 2020)
• Extension of the CURLEAD code for modelling various pulsed operations of the JT-60SA type HTS current lead and comparison to a REBCO current lead (with Karlsruhe Insitute of Technology, Decemeber 2016 - October 2017)
• Modelling of pulsed scenario for 20 kA JT-60SA current lead and comparison to a REBCO current lead (with Karlsruhe Insitute of Technology, February 2016 - December 2016)
• Update of the thermo-hydraulic analysis of the Vacuum vessel regular sector (with Fusion For Energy - F4E, July 2014 - January 2015)
• Thermo-hydraulic analysis of three test vehicles for the Gyrotron cavity (with Fusion For Energy - F4E, June 2014 - January 2015)
• Thermohydraulic optimization of the hypervapotron cooling concept used in the gyrotron collector (with Fusion For Energy - F4E, July 2013 - January 2015)
• Thermohydraulic analysis of the VV field joints (with Fusion For Energy - F4E, April 2013 - September 2013)
• Thermohydraulic optimization of the FW panel FW06 (with Fusion For Energy - F4E, March 2012 - September 2012)
• Thermal modeling of the ITER TF coils to assess neutron radiation shielding design and development of a simplified ITER magnet system thermal response model (with ITER Organization, March 2012 - September 2013), continued in: Thermal modeling of the ITER TF Coils to assess neutron radiation shielding design (with ITER Organization, June 2014 - December 2014)
• Thermohydraulic analysis of the VV irregular sector (with Fusion For Energy - F4E, February 2012 - August 2012)
• Thermal-hydraulic analysis of the VV regular sector and triangular support (with Fusion For Energy - F4E, July 2011 - March 2012)
• Thermal-fluid-dynamic analysis of ITER superconducting cable tested with soldered joints (with Alma Mater Studiorum - Università di Bologna, March 2010 - June 2010)