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Support to Nuclear Safety and Engineering for ITER Fusion Reactor (2018-2025)

    Multi-year contract to provide ITER with support services in the area of nuclear safety and engineering for the Electron Cyclotron (EC) and the Ion Cyclotron (IC) Heating and Current Drive (H&CD) system antennas. Involved areas and competences:
  • Computational Fluid Dynamics
  • Thermal-hydraulics
  • Radiation shielding
  • Mechanical engineering
  • Instrumentation & Control
  • Design of pressure equipment
  • ITER fusion reactor

Support to Nuclear Decommissioning & Waste Management for JRC ISPRA (2018-2026)

    Eight-year contract to provide the European Joint Research Centre (JRC) in Ispra (Italy) with engineering services in the area of Decommissioning and Waste Management (D&WM) of nuclear installations. Involved areas and competences:
  • Thermal-hydraulics
  • Mechanical engineering
  • Computational Fluid Dynamics
  • Instrumentation & Control
  • Design of equipment
  • Rad-Waste treatment and conditioning
  • Radiation shielding
  • Radiological accidents (radioisotopes release), consequences and mitigation
  • Quality assurance
  • Compliance with regulatory framework

Containment Venting Analysis for Atucha-1 NPP (2014 – 2016)

  • Development of GOTHIC model for Atucha-1 NPP containment aimed at evaluating:
    • - Pressure & temperature response
    • - Hydrogen distribution
    • - Water hold-up
  • Support NASA to develop possible accident management procedures

Support for Containment Thermal-hydraulic Analysis (2015-2016)

  • Training CNNC/CNPE staff
  • Containment Analysis
  • Review of ACP1000 containment models

Development of PUSPATI TRIGA Research Reactor Evaluation Model and Thermal Hydraulics Analysis (2015-2016)

  • Support and guidance in development of System Thermal Hydraulic model for the Puspati Research Reactor to be used for licensing calculations

Support to Safety Assessment and Education (SAET) Project of IAEA (2011-2016)

  • Lectures and exercises on practical applications of thermal-hydraulic system code calculations in safety assessment of nuclear facilities

Atucha-2 NPP: Licensing, Operation and Safety (2011-2012)

  • Characterization of the Licensing Approach
  • System Thermal-hydraulics (TH) Accident Analysis for licensing purpose
  • Analysis and implementation of the I&C of Atucha-2 NPP to perform full Best Estimate (BE) Thermal-hydraulics calculations
  • Subchannel analysis for licensing purpose
  • Reactor Physics Analysis including cross section generation for licensing purpose
  • Fuel Analysis in normal operation including on line refueling
  • Fuel Analysis in accident conditions for licensing purpose
  • Radiological consequences evaluation for licensing purpose.
  • CFD assessment of in-vessel flow distribution and pressure losses
  • Pressurized Thermal Shock analysis including TH and Structural Mechanics coupling

Atucha-2 NPP: Licensing, Operation and Safety (2012-2013)

  • Containment Analysis, associated with safety cases postulated events
  • Radiological consequences evaluation for licensing purpose
  • Quantification of Uncertainty for the BE calculations
  • Preparation and issuing of FSAR Chapter 15
  • Validation of derived Atucha-2 Evaluation Models
  • Preparation of additional support documents for Licensing approval
  • Design of experiment for Boron Injection Test Facility (BITF) including Instrumentation
  • BITF CFD and system TH analyses
  • Operation of the data acquisition system during the BITF experiments

Construction of the Critical Heat Flux Test Facility (CHF-TF) for CHF Measurements (2013-2015)

  • Test facility design according to ASME VIII division I and II
  • Design of electrical heater rod
  • Test facility operation for experimental Critical Heat flux investigation
  • Design of experimental test matrix
  • Subchannel analysis
  • Derivation of CHF correlations

Engineering services to perform technical studies for the LABGENE reactor core project verification (2014-2015)

  • System Thermal-hydraulic calculations with main focus on Reactor Pressure Vessel
  • Reactor Physics including cross section generation
  • Performing coupled Thermal-Hydraulics and Reactor Physics calculations
  • Fuel Analysis in normal operation and in accident conditions
  • To supply related consistent documentation to support CTMSP in finalizing the core design
  • To train staff as needed and to address (in cooperation with CTMSP) possible requests coming from Regulatory Authority

Thermal-Hydraulics, Severe Accident Analysis and Support for SAMG Development (2012 - 2013)

  • System Thermal-hydraulics Analysis
  • Containment Analysis
  • Severe accident Analysis
  • Developing models for supporting ACP1000
  • Training CNNC/CNPE staff

Development of the OPAL RR Core Model (2015-2016)

  • Development of state-of-the-art Evaluation Model (EM) of the Open Pool Australian Lightwater (OPAL) Research Reactor (RR)
  • Preparation and Issue of a Reference Data Set (focused on reactor core)
  • Development and qualification of the System Thermal-Hydraulics Model
  • Simulation of steady state calculations

Review of Sensitivity and Uncertainty Methods for Nuclear Safety Analysis (2015-2016)

  • To review the current status of sensitivity analysis theory and its applications in the nuclear industry, in particular in the context of deterministic safety analysis for licensing purposes
  • To review sensitivity analysis techniques for identification of cliff-edge effects
  • To provide recommendations on the possible future use of sensitivity analysis methods and tools in regulatory or licensing assessments

Expert Review of Containment Radionuclide Behavior (2014-2015)

  • Review of the aerosol transport/behavior models and their verifications for the SMART code
  • Verification of the simulations of the fission product behavior in containment

Analysis of containment system of Vandellós and Ascó NPP (2014-2015)

  • Investigation of thermal fluid dynamic behavior of the containment system of Vandellós and Ascó NPP during postulated accidental conditions and validation of MAAP results
  • Development of GOTHIC model of the containment aimed at evaluating pressure & temperature response
  • Development of GOTHIC model of the containment aimed at evaluating hydrogen distribution
  • Support to assess accident management procedures
  • Code-to-Code comparison against MAAP

Two-Phase Natural Circulation Instability Analysis for Passive Auxiliary Feed Water System (PAFS) in APR+ (2015)

  • To set-up System Thermal-Hydraulics PAFS nodalization suitable for two-phase passive system Natural Circulation stability analysis
  • To perform System Thermal-hydraulics simulations covering wide range of two-phase flow conditions
  • Development of PAFS Stability Map
  • To assess the performance and noticeably the stability of the PAFS system when the whole NPP model is considered, accounting for different Primary side thermal-hydraulics conditions
  • To provide recommendations on system improvements

Analysis of Condensation Phenomena during the activation of Vacuum Vessel Pressure Suppression System (VVPS) of the ITER Reactor (2015)

  • To assess VVPSS condensation capabilities by performing parametric study at prototypical conditions (noticeably sub-atmospheric conditions)
  • CFD Condensation Analysis
  • System Thermal-hydraulics Condensation Analysis
  • To provide recommendations on VVPSS design and on related experimental campaign

To assess the structural integrity of Kernkraftwerk Gundremmingen II (KRB-II) RPV against ASME code prescriptions (2015)

  • Structural Mechanic Analysis of RPV
  • Compliance with ASME Boiler and Pressure Vessel Code, Section III