Mechanical Behavior of Neutron Inrradiated High Cr Ferritic-Martensitic Steels

Abderrahim Al Mazouzi; Enrico Lucon; Hamid Aït Abderrahim

Mechanical Behavior of Neutron Inrradiated High Cr Ferritic-Martensitic Steels

Abderrahim Al Mazouzi, Enrico Lucon, Hamid Aït Abderrahim

Research output › peer-review

Abstract

High Chromium Ferritic-Martensitic steels are candidate materials for the target spallation source and the fuel cladding tubes in the European demonstrator of the accelerator driven system (ADS). In this work, we will present new results obtained from the irradiation campaign that has been performed in the BR2 reactor within the SPIRE project to assess the mechanical behaviour of several standard 9-12%Cr steels. The irradiations have been performed up to 4.5 dpa at 200°C. A quantitative assessment of the effects of neutron irradiation, in terms of both hardening ) and embrittlement is presented, based on the comparison with the unirradiated

Original language	English
Pages (from-to)	73-74
Journal	The Journal of The Minerals, Metals & Materials Society
Volume	2
Issue number	3
State	Published - 14 Oct 2005

Cite this

@article{aa24835df73d4b1da2b10e2000c87dac,

title = "Mechanical Behavior of Neutron Inrradiated High Cr Ferritic-Martensitic Steels",

abstract = "High Chromium Ferritic-Martensitic steels are candidate materials for the target spallation source and the fuel cladding tubes in the European demonstrator of the accelerator driven system (ADS). In this work, we will present new results obtained from the irradiation campaign that has been performed in the BR2 reactor within the SPIRE project to assess the mechanical behaviour of several standard 9-12%Cr steels. The irradiations have been performed up to 4.5 dpa at 200°C. A quantitative assessment of the effects of neutron irradiation, in terms of both hardening ) and embrittlement is presented, based on the comparison with the unirradiated",

keywords = "Nuclear materials and environmental effects",

author = "{Al Mazouzi}, Abderrahim and Enrico Lucon and {A{\"i}t Abderrahim}, Hamid",

note = "Score = 10",

year = "2005",

month = oct,

day = "14",

language = "English",

volume = "2",

pages = "73--74",

journal = "The Journal of The Minerals, Metals & Materials Society",

issn = "1047-4838",

publisher = "Springer",

number = "3",

}

TY - JOUR

T1 - Mechanical Behavior of Neutron Inrradiated High Cr Ferritic-Martensitic Steels

AU - Al Mazouzi, Abderrahim

AU - Lucon, Enrico

A2 - Aït Abderrahim, Hamid

N1 - Score = 10

PY - 2005/10/14

Y1 - 2005/10/14

N2 - High Chromium Ferritic-Martensitic steels are candidate materials for the target spallation source and the fuel cladding tubes in the European demonstrator of the accelerator driven system (ADS). In this work, we will present new results obtained from the irradiation campaign that has been performed in the BR2 reactor within the SPIRE project to assess the mechanical behaviour of several standard 9-12%Cr steels. The irradiations have been performed up to 4.5 dpa at 200°C. A quantitative assessment of the effects of neutron irradiation, in terms of both hardening ) and embrittlement is presented, based on the comparison with the unirradiated

AB - High Chromium Ferritic-Martensitic steels are candidate materials for the target spallation source and the fuel cladding tubes in the European demonstrator of the accelerator driven system (ADS). In this work, we will present new results obtained from the irradiation campaign that has been performed in the BR2 reactor within the SPIRE project to assess the mechanical behaviour of several standard 9-12%Cr steels. The irradiations have been performed up to 4.5 dpa at 200°C. A quantitative assessment of the effects of neutron irradiation, in terms of both hardening ) and embrittlement is presented, based on the comparison with the unirradiated

KW - Nuclear materials and environmental effects

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_27200

UR - http://knowledgecentre.sckcen.be/so2/bibref/2928

M3 - Article

SN - 1047-4838

VL - 2

SP - 73

EP - 74

JO - The Journal of The Minerals, Metals & Materials Society

JF - The Journal of The Minerals, Metals & Materials Society

IS - 3

ER -