Sample component and method for nuclear power plant reactor pressure container irradiation inspection test

Abstract

The invention discloses a sample component and method for a nuclear power plant reactor pressure container irradiation inspection test. The component comprises a tensile sample, an impact sample and a compact tensile sample, wherein the tensile sample is used for acquiring the tensile strength, the yield strength, the elongation and the cross section reduction ratio of irradiated materials, the impact sample is used for acquiring impact toughness of the irradiated materials, the compact tensile sample is used for acquiring fracture toughness of the irradiated materials and provided with notches, circular portions and side grooves which are sequentially formed in a first side face and a second side face from top to bottom, and the notch with an isosceles trapezoidal section, the circular portions and the notch with a V-shaped bottom jointly form an extensometer placement space. The method includes the steps of sample preparation, sample loading, sample testing and result evaluation. Arrangement of a bent sample is canceled, the quantity proportion of the other samples is optimized, the shape of the compact tensile sample is optimally improved, and test failure risks in fracture toughness testing are decreased.

Description

technical field [0001] The invention relates to the field of safe operation of reactor pressure vessels of nuclear power plants, in particular to a sample assembly and a test method for irradiation supervision tests of reactor pressure vessels of nuclear power plants. Background technique [0002] The reactor pressure vessel of a nuclear power plant is a closed container used to accommodate a nuclear reactor and withstand its huge operating pressure, which contains and supports the core nuclear fuel assembly, control assembly, reactor internals and reactor coolant. Due to its long-term service in strong irradiation, high temperature, and high pressure environments, it is prone to neutron radiation damage, which is specifically manifested in the increase in strength and decrease in toughness during the irradiation embrittlement of reactor pressure vessel steel, which further leads to the failure of reactor pressure vessel. [0003] In order to ensure the safety of the operati...

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Problems solved by technology

[0006] 1. Due to the large size of the bending sample, it occupies the precious limited loading space in the irradiation supervision tube (the size of the bending sample is much larger than that of the compact tensile sample, and the volume of a bending sample (or occupies the space in the irradiation supervision tube) ) approximately corresponds to the volume of 13 compact tensile specimens);

[0007] 2. The existing design of compact tensile specimens cannot fully meet the test requirements of fracture toughness, and there are certain risks;

[0009] It can be seen that the setting method of the radiation supervision sample and the design scheme of the compact tensile sample in the above-mentioned prior art can no longer meet the requirements of radiation supervision. The sample components and test methods of the container irradiation supervision test enable it to optimize the quantity ratio of various samples under the premise of meeting the requirements of regulations and standards, in order to obtain more and effective mechanical properties of radiation supervision samples data, and improve the shape of the existing compact tensile specimen so that it can better meet the test requirements and reduce the risk in the fracture toughness test

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