TY - JOUR
T1 - Characterisation of the fracture properties in the ductile to brittle transition region of the weld material of a reactor pressure vessel
AU - Scibetta, Marc
AU - Ferreño, Diego
AU - Gorrochategui, Iñaki
AU - Lacalle, Roberto
AU - van Walle, Eric
AU - Javier, Martín
AU - Gutiérrez-Solana, Federico
N1 - Score = 10
PY - 2011/4
Y1 - 2011/4
N2 - The tests consisted of Charpy impact and tensile tests, performed in the framework of the surveillance programme of the plant. Moreover, in the context of this research, K Jc fracture toughness tests on pre-cracked Charpy V notch specimens (evaluated according to the Master Curve methodology) together with some mini-tensile tests, were performed; non-irradiated and several irradiated material conditions were characterised. The analysis of the experimental results revealed some inconsistencies concerning the material embrittlement as measured through Charpy and K Jc fracture tests: in order to obtain an adequate understanding of the results, an extended experimental scope well beyond the regulatory framework was developed, including Charpy tests and K Jc fracture tests, both performed on reconstituted specimens. Moreover, Charpy specimens irradiated in the high flux BR2 material test reactor were tested with the same purpose. With this extensive experimental programme, a coherent and comprehensive description of the irradiation behaviour of the weld material in the transition region was achieved. Furthermore it revealed better material properties in comparison with the initial expectations based on the information obtained in the framework of the surveillance programme.
AB - The tests consisted of Charpy impact and tensile tests, performed in the framework of the surveillance programme of the plant. Moreover, in the context of this research, K Jc fracture toughness tests on pre-cracked Charpy V notch specimens (evaluated according to the Master Curve methodology) together with some mini-tensile tests, were performed; non-irradiated and several irradiated material conditions were characterised. The analysis of the experimental results revealed some inconsistencies concerning the material embrittlement as measured through Charpy and K Jc fracture tests: in order to obtain an adequate understanding of the results, an extended experimental scope well beyond the regulatory framework was developed, including Charpy tests and K Jc fracture tests, both performed on reconstituted specimens. Moreover, Charpy specimens irradiated in the high flux BR2 material test reactor were tested with the same purpose. With this extensive experimental programme, a coherent and comprehensive description of the irradiation behaviour of the weld material in the transition region was achieved. Furthermore it revealed better material properties in comparison with the initial expectations based on the information obtained in the framework of the surveillance programme.
KW - Characterisation
KW - Charpy impact
KW - Charpy specimen
KW - Charpy tests
KW - Charpy v notches
KW - Ductile to brittle transitions
KW - Fracture property
KW - Fracture test
KW - Fracture toughness tests
KW - High flux
KW - Irradiated materials
KW - Irradiation behaviour
KW - Master curve
KW - Material property
KW - Material test reactors
KW - Reactor Pressure Vessel
KW - Reconstituted specimens
KW - Regulatory frameworks
KW - Tensile tests
KW - Transition regions
KW - Weld material
UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_123762
UR - http://knowledgecentre.sckcen.be/so2/bibref/9457
U2 - 10.1016/j.jnucmat.2011.01.024
DO - 10.1016/j.jnucmat.2011.01.024
M3 - Article
SN - 0022-3115
VL - 411
SP - 25
EP - 40
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
IS - 1-3
ER -