Material performance testing device for key nuclear material under complex service environment

Abstract

The invention relates to a material performance testing device for a key nuclear material under a complex service environment, and belongs to the technical field of material performance testing. The material performance testing device is mainly composed of a machine frame module, a lifting device, a bend loading module, an in-situ observing module, a reaction kettle module and a stretch loading module. The material performance testing device disclosed by the invention can achieve stretching-bending combined load loading and coupled loading of a supercritical water strong oxidation corrosion environment, can more really simulate a real work condition of the in-pile key nuclear material of a supercritical water reactor, and can further research micro mechanical properties of the key nuclear material. According to the material performance testing device disclosed by the invention, a modularization design is utilized, and the in-situ observing module is integrated; thus, the material performance testing device has the advantages of simple structure, compact layout and the like, microstructure of a material surface can be monitored, a material corrosion behavior can be reflected in real time, and an effective testing method for researching internal relation between microstructure morphology and macro mechanical property of the material and an initiation and propagation law of a stress corrosion crack is provided.

Description

technical field [0001] The invention relates to the technical field of material performance testing, and is used for a material performance testing device for key nuclear materials in complex service environments. Background technique [0002] As a clean energy, nuclear power has become an important part of the power industry, and nuclear power construction is being actively promoted at home and abroad. As the only nuclear reactor that uses light water as a coolant, the Supercritical Water Reactor (SCWR), it is one of the most promising fourth-generation (GEN-IV) concept reactor types that can be used to generate nuclear energy. The steam uses a direct cycle method to drive a turbo generator to generate electricity, and has the advantages of high thermal efficiency and simplified nuclear power plant construction. [0003] The coolant of SCWR is supercritical water (SCW) exceeding the critical point of water (374°C, 22.1MPa), which has extremely high requirements on the stru...

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Problems solved by technology

[0006] The object of the present invention is to provide a material performance test device for key nuclear materials in complex service environments, to simulate the material performance test of the SCWR reactor environment, and to solve the problem of the single load applied by the existing related material testing machines and the

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