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#
|
Case Study Description |
Code and Methodology
Development & Validation
|
Licensing Applications
|
Independent Assessment
(Safety and Design)
| Experimental Activities |
Technical Area
|
Reference Technology
|
2
|
Atucha II Fast Boron Injection Test Facility: Contribution to Design & Supply of Instrumentation |
|
 |
|
|
EXP, FSM, PTH |
PHWR |
4
|
CFD Studies in Support of Atucha II NPP Licensing |
|
|
|
|
FSM, CB, PTH, EXP |
PHWR |
| 7 |
Structural Mechanics Analyses in Support of Atucha II NPP Licensing |
|
|
|
|
FSM, PTH, EXP |
PHWR |
| 8 |
HPR-1000 Development of Emergency Operating Procedures |
|
|
|
|
PTH |
LWR |
| 9 |
VVER-1000 Safety Analysis: Experimental Tests for Code Qualification |
|
|
|
|
PTH |
VVER |
| 10 |
VVER-1000 non-LOCA Accident Management |
|
|
|
|
PTH |
VVER |
| 11 |
VVER-1000 SBLOCA Accident Management |
|
|
|
|
PTH |
VVER |
| 12 |
VVER-1000 Severe Accident Analysis |
|
|
|
|
SA |
VVER |
| 13 |
VVER-1000 HELB Safety Analysis |
|
|
|
|
CB, PTH |
VVER |
| 14 |
VVER-1000 3D Neutron Kinetics Simulations |
|
|
|
|
CB |
VVER |
| 15 |
VVER-1000 Pressurized Thermal Shock Analysis |
|
|
|
|
PTH, FSM |
VVER |
| 16 |
RELAP5 Simulation of Darlington NGSLoss of Flow Event |
|
|
|
|
PTH |
CANDU |
| 17 |
7RBMK Safety Assessmen |
|
|
|
|
PTH |
RBMK |
| 19 |
Two-phase Natural Circulation Instability Analysis for Passive Auxiliary Feedwater System (PAFS) in APR+ |
|
|
|
|
PTH |
GEN III |
| 21 |
SMART Code Independent Assessment |
|
|
|
|
PTH, SA |
CANDU |
| 22 |
Critical Heat Flux Test Facility Design and Construction |
|
|
|
|
EXP, FSM, PTH |
LWR, SMR |
| 23 |
Atucha I Containment Analysis for Severe Accident Management |
|
|
|
|
SA |
PHWR |
| 25 |
Design of Screens toMinimize the Impact of MethaneDispersion from Gas Distribution Pipelines |
|
|
|
|
FSM |
IND |
| 26 |
Fire Hazard Analysis for ITER Fusion Reactor Building Compartments |
|
|
|
|
FSM |
Fusion |
| 27 |
ITER Vacuum Vessel Pressure Suppression System Design Assessment |
|
|
|
|
FSM |
Fusion |
| 28 |
Support to Nuclear Safety and Engineering for ITER Fusion Reactor |
|
|
|
|
FSM, PTH, EXP |
Fusion |
| 29 |
Independent Analysis for OPAL Research Reactor Power Uprate |
|
|
|
|
PTH |
RR |
| 30 |
KRB-II Reactor Pressure Vessel Structural Integrity Assessment |
|
|
|
|
FSM |
LWR |
| 34 |
ASCO NPP Containment Analysis |
|
|
|
|
FSM, PTH |
LWR |
