Prediction of Irriadiation Damage Effects on Reactor ComponentsSupervisor: prof. Ing. Vladimír Slugeň, DrSc.
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|Project description:||Reactor pressure vessel (RPV) embrittlement poses one of limiting factors in the lifetime of today?s NPP. Properties of the RPV are routinely checked and verified by macroscopic methods such as Charpy V-notch and tensile tests. Our task was in this running 6th framework project is a contribution in the creation of sophisticated database according to existing experimental results from different methods (PAS, MS, SANS, TEM, HV10, etc.) and application of suitable simulation methods (ab initio, MD, AKMC, OKMC). The attention is focused mostly on measurement of VVER reactor steel using positron annihilation spectroscopy and ab initio calculation of Fe-Ni composition|
|Kind of project:||6. rámcový program ()|
|Department:||Department of nuclear physics and technology (FEEIT)|
|Project identification:||PERFECT - FI6O-CT-2003-508840|
|Project status:||Successfully completed|
|Project start date :||01. 01. 2004|
|Project close date:||31. 12. 2007|
|Number of workers in the project:||2|
|Number of official workers in the project:||0|