Experimental device for flow and heat transfer characteristics of curved single passage of subcritical energy reactor coolant

A technology of heat transfer characteristics and experimental device, which is applied in the field of a new type of experimental device for heat transfer characteristics of a curved single-channel flow of coolant in a nuclear reactor, and can solve problems such as the inability to simulate the flow and heat transfer characteristics of a subcritical cladding coolant.

Active Publication Date: 2015-03-11
NUCLEAR POWER INSTITUTE OF CHINA
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Problems solved by technology

The existing device cannot simulate the flow and heat transfer characteristics of the subcritical cladding coolant curved channel driven by the ITER device under the condition of circumferential

Method used

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  • Experimental device for flow and heat transfer characteristics of curved single passage of subcritical energy reactor coolant
  • Experimental device for flow and heat transfer characteristics of curved single passage of subcritical energy reactor coolant
  • Experimental device for flow and heat transfer characteristics of curved single passage of subcritical energy reactor coolant

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Embodiment 1

[0026] Such as Figure 1 to Figure 3 shown.

[0027] Based on the ITER-driven subcritical mixed reactor fuel cladding curve equation, the present invention selects the curved channel with the largest curvature and the highest steam content near the inner cladding outlet as a typical curved geometric characteristic for the purpose of thermal safety research. The invention utilizes direct current heating to heat the eccentric bend pipes with different circumferential wall thicknesses to realize circumferential non-uniform heating, so as to simulate the circumferential non-uniform distribution characteristics of heat flux density in subcritical reactor coolant channels. The inner diameter of the runner is consistent with the inner diameter of the subcritical reactor coolant channel ( φ =16 mm), the outer diameter and eccentricity of the eccentric elbow are determined by the structural strength requirements and heat flux distribution requirements. The eccentric bend is obtained ba...

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Abstract

The invention discloses an experimental device for flow and heat transfer characteristics of a curved single passage of a subcritical energy reactor coolant. The experimental device comprises a curved heating single tube, wherein the two ends of the heating single tube are communicated with stabilizing straight tubes, and the stabilizing straight tubes are communicated with threaded joints, the threaded joint are sleeved with threaded flanges; the stabilizing straight tubes are welded with powered copper bars, and pressure diversion holes are formed in the stabilizing straight tubes; the heating single tube is an eccentric curved tube or a concentric curved tube; the center of an inside diameter circle of the eccentric curved tube is O1, the center of an outside diameter circle of the eccentric curved tube is O2, the distance between the O1 to the O2 is larger than zero, and a line segment for connecting the O1 to the O2 is O1O2; the eccentric curved tube is welded with a thermocouple, and a heat insulation protection structure is arranged on the outer wall of the eccentric curved tube; the center of an inside diameter circle of the concentric curved tube and the center of an outside diameter circle of the concentric curved tube are overlaid at a point X1, a plurality of thermocouples are welded on the outer wall of the concentric curved tube, and a heat insulation protection structure is arranged on the outer wall of the concentric curved tube. The experimental device can provide experiment support for the feasibility study on a thermo-hydraulic design of the subcritical reactor coolant.

Description

technical field [0001] The invention relates to a novel nuclear reactor coolant curved single-channel flow heat transfer characteristic experimental device, in particular to an experimental device for simulating the typical curved single-channel flow heat transfer characteristic of mixed reactor subcritical energy cladding coolant. It belongs to the field of new energy development of fusion-driven fission reactors, specifically, it belongs to the field of experimental technology necessary for the verification of thermal hydraulic design and the formulation of thermal safety rules. Background technique [0002] After the Fukushima nuclear accident in Japan, the safety of fission reactors has been questioned; coupled with the difficulty of waste disposal, limited fuel reserves and nuclear proliferation issues, fission nuclear reactors are difficult to meet the long-term energy needs of mankind. With the current technical conditions, pure deuterium-tritium fusion commercial nuc...

Claims

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Application Information

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IPC IPC(8): G01N25/20
Inventor 幸奠川彭劲枫黄彦平徐建军刘文兴刘亮杨祖毛
Owner NUCLEAR POWER INSTITUTE OF CHINA
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