Testing system and method for heat-transfer properties of engineering magnitude-order double-layered molten pool of nuclear reactor

A technology for a nuclear reactor and a test system, which is applied in the field of a nuclear reactor engineering-level double-layer molten pool heat transfer characteristic test system, can solve problems such as failure to obtain the natural convection heat transfer relationship of the molten pool, and inability to simulate the heat transfer characteristics of the double-layer molten pool.

Inactive Publication Date: 2019-03-26
XI AN JIAOTONG UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

However, this study was only carried out on the upper metal layer, and the natural convection heat transfer relationship of the melting pool was not obtained, let alone the heat transfer characteristics of the double-layer melting pool.

Method used

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  • Testing system and method for heat-transfer properties of engineering magnitude-order double-layered molten pool of nuclear reactor
  • Testing system and method for heat-transfer properties of engineering magnitude-order double-layered molten pool of nuclear reactor
  • Testing system and method for heat-transfer properties of engineering magnitude-order double-layered molten pool of nuclear reactor

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Embodiment Construction

[0032] Below in conjunction with accompanying drawing and specific embodiment the present invention is described in detail:

[0033] Such as figure 1 As shown, the present invention relates to a nuclear reactor engineering level double-layer molten pool heat transfer characteristic test system, including the main water pump 2 on the main circuit and the first soft joint 401 and the first Y-type filter on the upstream pipeline of the main water pump 2 301, the first valve 101 on the upstream pipeline of the first Y-type filter 301 and its upstream water storage tank 1; the downstream pipeline of the main water pump 2 is connected with a second flexible joint 402, through the first flexible joint 401 and the second flexible joint 402 The cooperation of the main water pump 2 to slow down the pipeline vibration caused by the fluid at the outlet of the main water pump 2; a tee joint is installed on the downstream pipeline of the second soft joint 402, and the two outlets of the tee...

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Abstract

The invention provides a testing system and method for heat-transfer properties of an engineering magnitude-order double-layered molten pool of a nuclear reactor. The system comprises a main loop composed of a water storage tank, a testing section, a main water pump and a related pipeline valve, a cooling loop composed of a cooling tower, an auxiliary water pump, a heat exchanger and a related pipeline valve, a molten salt loop composed of a molten salt furnace, a vacuum pump and a related pipeline valve, a heat-conducting oil loop composed of a heat-conducting oil tank, a recycling groove anda related pipeline valve, a heating module, a data measurement and acquisition module, an image acquisition and analysis module and a control module; the invention further provides the testing methodof the system. According to the testing system and method, a natural convection heat exchange test of the double-layered structural molten pool (an upper metal layer and a lower oxidization molten pool) of the nuclear reactor under a severe accident is carried out to obtain upward and downward heat-transfer properties of the oxidization molten pool and the heat-transfer properties of a side wallof the metal layer, and reference can be provided for engineering practice and application of a reactor core melt retention technology (IVR).

Description

technical field [0001] The invention relates to the technical field of research on the natural convection heat transfer characteristics of molten pools under severe accident conditions in nuclear power plants, and in particular to a test system and method for the heat transfer characteristics of nuclear reactor engineering-level double-layer molten pools. 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 relat...

Claims

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Application Information

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Patent Type & Authority Applications(China)
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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