Experimental device and method for simulating the retention of melt in the nuclear reactor core after melting

Abstract

The invention discloses an experiment device for simulating retention of in-pile melts obtained by melting of a reactor core of a nuclear reactor and an experiment method. The device consists of a copper heating section, a quartz glass component and a data measurement system. According to the experiment device, a melt hard shell of the reactor core is simulated through a semispherical copper ball shell; decay heat is simulated through a spiral heating wire embedded into the semispherical shell; the inner wall surface of a lower enclosure of a pressure container is simulated through quartz glass, and therefore, a flowing heat exchange phenomenon of a narrow gap between the inner wall surface of the pressure container of the reactor and the melt hard shell can be simulated, and the influence on the retention of the in-pile melts caused by flowing of water in the narrow gap can be researched. The experiment device has the advantages of visible experiment process, high experiment precision, high safety, easiness in operation and the like. A running practice shows that the experiment device runs stably and can thoroughly meet a design requirement.

Description

technical field [0001] The invention belongs to the technical field of experimental devices, and in particular relates to an experimental device and method for simulating the retention of molten matter in a nuclear reactor core after melting. Background technique [0002] After the serious accident of reactor core melting, the pressure vessel becomes an important barrier to prevent the escape of radioactive materials. In 1979, the Three Mile Island Nuclear Power Plant had a serious core meltdown accident. In the analysis of this accident, all the well-known safety analysis software calculation results showed that the lower head of the pressure vessel would fail, resulting in molten material overflowing the pressure vessel. However, the pressure vessel did not fail during the accident, which indicates that a new cooling mechanism existed and effectively cooled the lower head of the reactor pressure vessel. Through previous theoretical and experimental studies at home and abr...

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Problems solved by technology

However, this device also has the disadvantages of the above-mentioned device, such as the inability to study the influence of water flow on phenomena such as critical heat flux, and the inability to conveniently lift the hemispherical copper shell, etc.

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