Neutron irradiation hardening of ODS alloy tested by miniature disk bend test method

2000 ◽  
Vol 283-287 ◽  
pp. 1011-1013 ◽  
Author(s):  
C.Q Chen ◽  
J.G Sun ◽  
Y.C Xu
Keyword(s):  
Neutron Irradiation ◽  
Test Method ◽  
Bend Test ◽  
Irradiation Hardening ◽  
Ods Alloy

Irradiation hardening and ductility loss of Eurofer97 steel variants after neutron irradiation to ITER-TBM relevant conditions

2021 ◽  
pp. 112935
Author(s):  
Arunodaya Bhattacharya ◽  
Xiang Chen ◽  
Tim Graening ◽  
Josina W. Geringer ◽  
Jordan Reed ◽  
...  
Keyword(s):  
Neutron Irradiation ◽  
Irradiation Hardening ◽  
Ductility Loss

scholarly journals Neutron irradiation hardening across ITER diverter tungsten armor

2020 ◽  
pp. 105437
Author(s):  
D. Terentyev ◽  
C. Yin ◽  
A. Dubinko ◽  
C.C. Chang ◽  
J.H. You
Keyword(s):  
Neutron Irradiation ◽  
Irradiation Hardening

Effects of Neutron Irradiation and Thermal Aging on Mechanical Properties of ODS Ferritic Steels for Advanced Nuclear Systems

2007 ◽  
Vol 561-565 ◽  
pp. 1773-1776 ◽  
Author(s):  
Ryuta Kasada ◽  
Hang Sik Cho ◽  
Naoyuki Okuda ◽  
Akihiko Kimura
Keyword(s):  
Neutron Irradiation ◽  
Thermal Aging ◽  
Charpy Impact ◽  
Oxide Dispersion Strengthened ◽  
Tensile Tests ◽  
Total Elongation ◽  
Ferritic Steels ◽  
Dislocation Loops ◽  
Irradiation Hardening ◽  
Nuclear Systems

Effects of neutron irradiation and thermal aging on the tensile properties and Charpy impact properties of oxide dispersion strengthened (ODS) ferritic steels for advanced nuclear systems were investigated and discussed with the results of microstructural observation. After the neutron irradiation in JMTR, significant hardening after irradiation at 290 and 400 °C as well as thermal aging at 500 °C, while no effect was observed after irradiation at 600 °C. While the irradiation hardening was not accompanied by a reduction of total elongation in tensile tests, Charpy impact energy at room temperature was reduced after the irradiation. The hardening after the irradiation at 400 °C and the aging at 500 °C was probably due to the formation of Cr-rich phases. The irradiation hardening observed in the ODS ferritic steels irradiated at 290 °C was well explained by the formation of dislocation loops.

Irradiation Hardening of Austenitic Stainless Steels: From Field Experience to Modeling

2004 ◽  
Author(s):  
C. Pokor ◽  
Y. Thebault ◽  
C. Pujol ◽  
J.-P. Massoud ◽  
D. Loisnard ◽  
...  
Keyword(s):  
Neutron Irradiation ◽  
Stainless Steels ◽  
Austenitic Stainless Steels ◽  
Pressurized Water Reactors ◽  
Iterative Approach ◽  
Pressurized Water ◽  
Irradiation Hardening ◽  
The Core ◽  
Water Reactors ◽  
Life Predictions

Materials for the core internals of Pressurized Water Reactors (austenitic stainless steels) are submitted to neutron irradiation. To understand the ageing mechanisms associated to irradiation and propose life predictions of the component, a multi step iterative approach consisting in particular in modeling the evolution of the hardening has been undertaken. Combination of characterization and modeling of simplified situations and field expertise is proposed.

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