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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
|
1
|
BEPU Safety Demonstration for Atucha II NPP Licensing |
|
|
|
|
PTH,CB,FSM,SA |
PHWR |
2
|
Atucha II Fast Boron Injection Test Facility: Contribution to Design & Supply of Instrumentation |
|
|
|
|
EXP, FSM, PTH |
PHWR |
3
|
Analysis of Large Break LOCA in Atucha II NPP |
|
|
|
|
PTH, CB, FSM, SA |
PHWR |
4
|
CFD Studies in Support of Atucha II NPP Licensing |
|
|
|
|
FSM, CB, PTH, EXP |
PHWR |
5 |
Reactor Physics Analysis for Atucha II NPP |
|
|
|
|
CB |
PHWR |
6 |
Atucha II -DBA Analysis for Licensing |
|
|
|
|
PTH |
PHWR |
7 |
Structural Mechanics Analyses in Support of Atucha II NPP Licensing |
|
|
|
|
FSM, PTH, EXP |
PHWR |
18 |
LABGENE Core Design Review |
|
|
|
|
CB, PTH |
LWR, SMR |
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 |
31 |
NPP Design Technical Evaluation following IAEA Standards: APR1400, VVER-1200, OPR-1000, E-CANDU-6, AP1000, CP1000 |
|
|
|
|
PTH, CB, FSM, SA |
GEN III |
32 |
Review of NPPLicensing Documentation on Behalf of IAEA |
|
|
|
|
PTH |
GEN III, SMR |
33 |
Drafting of Guidelines for Review of Deterministic Safety Analysis for Design Extension Conditions |
|
|
|
|
PTH, SA |
GEN III |
35 |
Safety Analysis of Facility for Treatment and Conditioning of Radwaste |
|
|
|
|
SA |
RAW |
36 |
Nuclear Decommissioning & Waste Management Support atJRC Ispra |
|
|
|
|
PTH, CB, FSM, SA |
RAW |