The microstructures and physical properties of the austenitic Cr18Ni9-grade steel after 22 and 33 years of operation as part of the reactor internals were tested for assessing the conditions of the BN-600 reactor non-replaceable components (internals) and the potential of their subsequent use in predicting the reactor ultimate life. The paper presents histograms of the porosity distribution depending on the void size, in samples taken from portions that were subjected to neutron irradiation with displacement rates ranging from 1.0×10–9 to 4.3×10–8 dpa/s at temperatures from 370 to 440 °C. The elasticity characteristics were measured by resonance-type ultrasonic technique for the samples taken from the same portions of material. It was demon...
Irradiation embrittlement of the neutron shield tank (NST) A212 Grade B steel from the Shippingport ...
This is the first semiannual progress report for the Reliability of Reactor Materials Program, funde...
Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power...
Welded steel components in the primary circuit in nuclear power plants (NPP) like pressure vessels a...
International audienceDue to their good corrosion resistance and excellent creep properties between ...
Many R&D programs are being conducted worldwide to study and, in some cases, develop materials with ...
International audienceIn PWR's, internals made of austenitic stainless steels (Cold Worked (CW) 316 ...
As many pressurized water reactors (PWRs) age and life extension of the aged plants is considered, v...
International audienceThe lower core internals, notably made in Solution Annealed (SA) 304 austeniti...
The most important effect of the degradation by neutron irradiation is a decrease in the ductility o...
The integrity assessment of the Reactor Pressure Vessel (RPV) is essential for the safe and Long Ter...
The proton irradiation behaviors of two kinds of SA-738Gr.B steels prepared by different heat treatm...
A new method predicting long-term thermal embrittlement of steel caused by P segregation is verified...
In this project, the post-irradiation microstructures and mechanical properties of two types of Fe-C...
The possibility of extending the operational life of reactor pressure vessels (RPV) up to 80 years p...
Irradiation embrittlement of the neutron shield tank (NST) A212 Grade B steel from the Shippingport ...
This is the first semiannual progress report for the Reliability of Reactor Materials Program, funde...
Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power...
Welded steel components in the primary circuit in nuclear power plants (NPP) like pressure vessels a...
International audienceDue to their good corrosion resistance and excellent creep properties between ...
Many R&D programs are being conducted worldwide to study and, in some cases, develop materials with ...
International audienceIn PWR's, internals made of austenitic stainless steels (Cold Worked (CW) 316 ...
As many pressurized water reactors (PWRs) age and life extension of the aged plants is considered, v...
International audienceThe lower core internals, notably made in Solution Annealed (SA) 304 austeniti...
The most important effect of the degradation by neutron irradiation is a decrease in the ductility o...
The integrity assessment of the Reactor Pressure Vessel (RPV) is essential for the safe and Long Ter...
The proton irradiation behaviors of two kinds of SA-738Gr.B steels prepared by different heat treatm...
A new method predicting long-term thermal embrittlement of steel caused by P segregation is verified...
In this project, the post-irradiation microstructures and mechanical properties of two types of Fe-C...
The possibility of extending the operational life of reactor pressure vessels (RPV) up to 80 years p...
Irradiation embrittlement of the neutron shield tank (NST) A212 Grade B steel from the Shippingport ...
This is the first semiannual progress report for the Reliability of Reactor Materials Program, funde...
Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power...