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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