PROJECTS

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

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

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

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

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)

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)

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)