Ziel
Demonstration of the continuing integrity of reactor pressure vessels (RPVs) requires the prediction of the ductile to brittle transition temperature (DBTT) of the vessel materials. Conventionally, irradiation induced changes in DBTT are monitored by the shifts in the transition behaviour measured in impact tests.
The assumption has then frequently been made that such shifts are equal to shifts in quasi-static fracture toughness.
However recent experimental results have shown that, for some materials, these two measures of the transition shift are not equal, and that in these circumstances impact shifts are often more closely equal to shifts in dynamic fracture toughness.
The present project is designed to obtain high quality data on different materials, so that a full comparison of Charpy impact shifts, dynamic fracture toughness shifts, and quasi-static fracture toughness shifts can be made. A wide range of reactor types of interest within Europe will be covered by the project and a comparison of properties between western and eastern materials will be possible.
The data will be compared with less complete datasets already available on a wider range of materials with the objective of obtaining a European consensus view of the behaviour of different materials. Micro-mechanical and micro-structural modelling will be employed to obtain a physical understanding of the relation between the different measures of the DBTT shift, and in particular to explain material-specific differences.
The project is organized in Tasks as follows:
Task 1: Preparation of material samples.
Task 2: Irradiation at the HFR Petten.
Task 3: Post Irradiation Examinations. PIE.
Task 4: Data analysis and Final Report.
Programm/Programme
Thema/Themen
Aufforderung zur Vorschlagseinreichung
Data not availableFinanzierungsplan
CSC - Cost-sharing contractsKoordinator
GL4 7RS Gloucester
Vereinigtes Königreich