The influence of nickel on the neutron irradiation embrittlement of Ni-Mo-Cr reactor pressure vessel (RPV) steels was investigated using alloys containing nickel in the range of 0.9-3.5 wt%. In all investigated alloys, the neutron irradiation with two dose conditions of 4.5 x 10(19) neutron/cm(2) at 290 A degrees C and 9.0 x 10(19) neutron/cm(2) at 290 A degrees C, respectively, increased the hardness and ductile-to-brittle transition temperature (DBTT). However, the increases of the hardness and DBTT resulting from the neutron irradiation were primarily affected by the irradiation dose that is closely related to the generation of irradiation defects, but not by the nickel content. In addition, a linear relationship between the changes in t...
Data on the neutron-induced swelling of simple Fe-Ni-Cr austenitic alloys are presented to show that...
Effect of neutron radiation exposure was investigated in various ferritic steels with the main empha...
The possibility of extending the operational life of reactor pressure vessels (RPV) up to 80 years p...
AUSTENITIC STAINLESS STEELS IN WHICH NICKEL IS SUBSTITUTED BY MANGANESE, ARE CURRENTLY UNDER STUD...
The deep understanding of the irradiation embrittlement of the pressure vessel of nuclear reactors i...
The Reactor Pressure Vessel (RPV) material of Nuclear Power Plants (NPP) is exposed to neutron irrad...
The deep understanding of the irradiation embrittlement of the pressure vessel of nuclear reactors i...
© 2016 Institute of Materials, Minerals and Mining. The effects of neutron radiation on nickel-based...
The present work is aimed to investigate the role and influence of certain elements as Cr, Ni, Mn an...
This paper presents the effects of neutron irradiation on the fracture behavior and deformation micr...
Nickel is an essential alloying element in steels used as structural materials in the most common nu...
Ferritic/martensitic steels such as the conventional 9Cr-1MoVNb (Fe-9Cr-1Mo-0.25V-0.06Nb-0.1C) and 1...
Initial results are reported from a study aimed to investigate the role and influence of the element...
In this paper we report initial results from a study focused on investigation of the role of element...
A comparison between pearlitic 2CrMoV steel (WWER-440) and 9% Cr based ferritic-martensitic steels (...
Data on the neutron-induced swelling of simple Fe-Ni-Cr austenitic alloys are presented to show that...
Effect of neutron radiation exposure was investigated in various ferritic steels with the main empha...
The possibility of extending the operational life of reactor pressure vessels (RPV) up to 80 years p...
AUSTENITIC STAINLESS STEELS IN WHICH NICKEL IS SUBSTITUTED BY MANGANESE, ARE CURRENTLY UNDER STUD...
The deep understanding of the irradiation embrittlement of the pressure vessel of nuclear reactors i...
The Reactor Pressure Vessel (RPV) material of Nuclear Power Plants (NPP) is exposed to neutron irrad...
The deep understanding of the irradiation embrittlement of the pressure vessel of nuclear reactors i...
© 2016 Institute of Materials, Minerals and Mining. The effects of neutron radiation on nickel-based...
The present work is aimed to investigate the role and influence of certain elements as Cr, Ni, Mn an...
This paper presents the effects of neutron irradiation on the fracture behavior and deformation micr...
Nickel is an essential alloying element in steels used as structural materials in the most common nu...
Ferritic/martensitic steels such as the conventional 9Cr-1MoVNb (Fe-9Cr-1Mo-0.25V-0.06Nb-0.1C) and 1...
Initial results are reported from a study aimed to investigate the role and influence of the element...
In this paper we report initial results from a study focused on investigation of the role of element...
A comparison between pearlitic 2CrMoV steel (WWER-440) and 9% Cr based ferritic-martensitic steels (...
Data on the neutron-induced swelling of simple Fe-Ni-Cr austenitic alloys are presented to show that...
Effect of neutron radiation exposure was investigated in various ferritic steels with the main empha...
The possibility of extending the operational life of reactor pressure vessels (RPV) up to 80 years p...