CASE STUDIES

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CASE STUDIES


This section collects a series of Case Studies performed by NINE experts. As “Case Studies,” they include specific and well-defined technical activities carried out in the framework of service contracts, with a diverse range of scopes and objectives and generally involving skills and competences from different technical areas.
In order to assist the reader with identifying the Case Studies of interest, a cross-reference table has been developed where each Case Study is assigned one or more of the following attributes:
•    Code and Methodology Development and Validation;
•    Licensing Applications;
•    Independent Assessment (Safety and Design);
•    Experimental Activities;
and indication is given of the relevant
•    Technical Area, and
•    Reference Technology.


CASE STUDIES DESCRIPTION

1    BEPU Safety Demonstration for Atucha II NPP Licensing      
 
     
2 Atucha II Fast Boron Injection Test Facility: Contribution to Design & Supply of Instrumentation      
 
     
3 Analysis of Large Break LOCA in Atucha II NPP      
 
     
4 CFD Studies in Support of Atucha II NPP Licensing      
 
     
5 Reactor Physics Analysis for Atucha II NPP      
 
     
6 Atucha II - DBA Analysis for Licensing       
 
     
7 Structural Mechanics Analyses in Support of Atucha II NPP Licensing       
 
     
8 HPR-1000 Development of Emergency Operating Procedures       
 
     
9 VVER-1000 Safety Analysis: Experimental Tests for Code Qualification       
 
     
10 VVER-1000 non-LOCA Accident Management      
 
     
11 VVER-1000 SBLOCA Accident Management       
 
     
12 VVER-1000 Severe Accident Analysis       
 
     
13 VVER-1000 HELB Safety Analysis       
 
     
14 VVER-1000 3D Neutron Kinetics Simulations       
 
     
15 VVER-1000 Pressurized Thermal Shock Analysis       
 
     
16 RELAP5 Simulation of Darlington NGS Loss of Flow Event       
 
     
17 RBMK Safety Assessment       
 
     
18 LABGENE Core Design Review      
 
     
19 Two-phase Natural Circulation Instability Analysis for Passive Auxiliary Feedwater System (PAFS) in APR+       
 
     
20 EBR-II SHRT-17 Test Thermal-Hydraulic Simulation       
 
     
21 SMART Code Independent Assessment       
 
     
22 Critical Heat Flux Test Facility Design and Construction       
 
     
23 Atucha I Containment Analysis for Severe Accident Management       
 
     
24 Severe Accident Code Application to Sandia Spent Fuel Pool Tests       
 
     
25 Design of Screens to Minimize the Impact of Methane Dispersion from Gas Distribution Pipelines       
 
     
26 Fire Hazard Analysis for ITER Fusion Reactor Building Compartments       
 
     
27 ITER Vacuum Vessel Pressure Suppression System Design Assessment       
 
     
28 Support to Nuclear Safety and Engineering for ITER Fusion Reactor       
 
     
29 Independent Analysis for OPAL Research Reactor Power Uprate       
 
     
30 KRB-II Reactor Pressure Vessel Structural Integrity Assessment       
 
     
31 NPP Design Technical Evaluation following IAEA Standards: APR1400, VVER-1200, OPR-1000, E-CANDU-6, AP1000, CP1000       
 
     
32 Review of NPP Licensing Documentation on Behalf of IAEA       
 
     
33 Drafting of Guidelines for Review of Deterministic Safety Analysis  for Design Extension Conditions       
 
     
34 ASCO NPP Containment Analysis       
 
     
35 Safety Analysis of Facility for Treatment and Conditioning of Radwaste       
 
     
36 Nuclear Decommissioning & Waste Management Support at JRC Ispra