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Heat-transfer characteristic testing device for nuclear reactor engineering level dual-layer melting pool

A nuclear reactor and test device technology, which is applied in nuclear reactor monitoring, reactors, nuclear engineering, etc., can solve problems such as the inability to obtain the characteristic parameters of the molten pool, the small size, and the inability to reflect the solidification characteristics of the non-eutectic mixture of the molten material, etc.

Inactive Publication Date: 2019-03-22
XI AN JIAOTONG UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Due to the small size of the device, the characteristic parameters of the melt pool at the nuclear reactor engineering level cannot be obtained, and water, brine and paraffin oil cannot reflect the solidification characteristics of the real melt as a non-eutectic mixture

Method used

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  • Heat-transfer characteristic testing device for nuclear reactor engineering level dual-layer melting pool
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  • Heat-transfer characteristic testing device for nuclear reactor engineering level dual-layer melting pool

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Embodiment Construction

[0023] Below in conjunction with accompanying drawing and specific embodiment the present invention is described in detail:

[0024] like figure 1 As shown, the present invention relates to a nuclear reactor engineering level double-layer molten pool heat transfer characteristic test device, including a test section 1, a cover plate 2, an electric heating element 3, a partition plate 4 and a corresponding temperature measuring component 5. Test section 1 is a semicircular slice structure based on the lower head of the real reactor pressure vessel. It is welded by the front side wall 101, the rear side wall 102 and the arc wall 103, with a diameter of 4000mm and an inner width of 300mm. There is a rectangular quartz glass window 6 on the upper part of the front side wall 101, which is used to observe and record the convective heat transfer and hard shell condensation characteristics at the interface of the double-layer molten pool during the test. There are four lighting holes...

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Abstract

The invention discloses a heat-transfer characteristic testing device for a nuclear reactor engineering level dual-layer melting pool. The testing device comprises testing segments, a cover plate, electric heating elements, an insulation board and temperature testing components. The testing device can be used for researching the natural convection heat exchange characteristic of a nuclear reactorengineering level lower dual-layer melting pool (upper metal layer and lower oxidizing-melting pool) in order to get the upward and downward heat-transfer characteristics of the oxidizing-melting pooland the heat-transfer characteristics of a metal layer to a side wall under different working conditions, and analyze the influence of the thickness and height of the metal layer on the heat-transfercharacteristic of the dual-layer melting pool, so that an important basis is laid for the research on the thermal focusing effect of the metal layer. The testing device has the advantages of simple structure, high safety and high operability, and can meet the test requirement for the research on the heat-transfer characteristic of the nuclear reactor engineering level lower dual-layer melting pool.

Description

technical field [0001] The invention relates to the technical field of research on heat transfer characteristics of head melting pools under severe accidents in nuclear power plants, in particular to a nuclear reactor engineering-level double-layer melting pool heat transfer characteristic test device. Background technique [0002] When a serious accident occurs in a nuclear power plant pressurized water reactor, the core melt produced will migrate to the lower head of the pressure vessel to form a molten pool. The flow and heat transfer characteristics of the molten pool have an important impact on the heat load distribution on the wall of the lower head and the external cooling capacity, and are the focus of IVR in severe accident mitigation strategies. At present, some experimental studies on the heat transfer characteristics of molten pools have been carried out at home and abroad, and the obtained heat transfer relations cannot meet the actual needs of nuclear reactors ...

Claims

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Application Information

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IPC IPC(8): G21C17/00
CPCG21C17/001Y02E30/30
Inventor 张亚培苏光辉周瑜琨田文喜秋穗正
Owner XI AN JIAOTONG UNIV
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