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Microstructural Characterization of Reactor Pressure Vessel Steels
Ion irradiation is a promising tool to emulate neutron-irradiation effects on reactor pressure vessel (RPV) steels, especially in the situation of limited availability of suitable neutron-irradiated material.
Libang Lai +4 more
doaj +3 more sources
Research Progress of Steels for Nuclear Reactor Pressure Vessels. [PDF]
The nuclear reactor pressure vessel is an important component of a nuclear power plant. It has been used in harsh environments such as high temperature, high pressure, neutron irradiation, thermal aging, corrosion and fatigue for a long time, which puts forward higher standards for the performance requirements for nuclear pressure vessel steel.
Zhou L +6 more
europepmc +3 more sources
The development of prediction model on irradiation embitterment for low Cu RPV steels [PDF]
The development of prediction model on irradiation embitterment (PMIE) of reactor pressure vessel (RPV) is an important method for nuclear reactor long term operation.
Chaoliang Xu +7 more
doaj +2 more sources
Safe and long term operation of nuclear reactors is one of the most discussed challenges in nuclear power engineering. The radiation degradation of nuclear design materials limits the operational lifetime of all nuclear installations or at least ...
Vladimír Slugeň +5 more
doaj +3 more sources
Comprehensive Toughness Dataset of Nuclear Reactor Structural Materials using Charpy V-Notch Impact Testing [PDF]
Reactor pressure vessel (RPV) steels are critical for maintaining the structural integrity and safety of nuclear reactors, designed to endure extreme conditions over prolonged operational lifetimes.
Isshu Lee +7 more
doaj +2 more sources
Spinodal decomposition and radiation damage of a FeCuMnNi high-entropy alloy
The precipitation of Cu-rich phases during the irradiation process will reduce radiation resistance in Fe-Cu-Mn-Ni reactor pressure vessel steels. Therefore, high-entropy alloys with excellent radiation resistance are expected to replace reactor pressure
Qingwei Guo +5 more
doaj +1 more source
The aim of this work is to present a new analytical model to evaluate jointly the mechanical integrity and the fitness-for-service of nuclear reactor pressure-vessels steels.
Alvaro Rodríguez-Prieto +4 more
doaj +1 more source
The small punch test is evaluated as a screening procedure for irradiation embrittlement of reactor pressure vessel steels. In particular, the correlation between ductile-to-brittle transition temperatures obtained from this small specimen test technique
E. Altstadt, F. Bergner, M. Houska
doaj +1 more source
Conducting local cutout from the surface of the VVER-1000 reactor vessel
Integrity of the reactor pressure vessel is a critical element in demonstrating the capability of nuclear power plant for operation to at least 80 years.
Олексій Геннадійович Руденко +3 more
doaj +5 more sources
The role of nickel in forming a structure providing increased service properties of reactor structural materials [PDF]
Nickel is an essential alloying element in steels used as structural materials in the most common nuclear power reactors of the VVER type. The paper considers reviews the results of structural studies of traditional and advanced materials of the vessels ...
Evgenia A. Kuleshova +5 more
doaj +3 more sources

