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Low-voltage high-power pressurized water reactor fuel assembly simulation device

A fuel assembly and simulation device technology, which is applied in the simulation process of specific applications, reactors, nuclear power generation, etc., can solve the problems of large energy consumption and complex structure of the device, and achieve the effect of reducing loss and cost and facilitating replacement

Active Publication Date: 2018-03-13
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0005] The technical problem to be solved by the present invention is that the device using stainless steel tubes to simulate fuel assemblies needs to be equipped with a corresponding high-voltage and high-power power supply, resulting in large energy consumption and complicated device structure. The purpose is to provide a low-voltage and high-power pressurized water reactor Fuel assembly simulation device, which meets the requirements of high-temperature and high-pressure experiments, and maintains thermal-hydraulic characteristics similarity with reactor fuel assemblies, can realize low-voltage, high-power PWR fuel assembly simulation process, consumes less energy, and simplifies the structure. It is used in the critical heat flux density and flow instability experiments of PWR fuel assemblies to verify the thermal safety performance of the reactor

Method used

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  • Low-voltage high-power pressurized water reactor fuel assembly simulation device
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  • Low-voltage high-power pressurized water reactor fuel assembly simulation device

Examples

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Effect test

Embodiment 1

[0030] like figure 1 As shown, a low-voltage high-power PWR fuel assembly simulation device includes a pressure-bearing assembly, an electric heating assembly 2, and a square flow channel, and the square flow channel is arranged in the pressure-containing assembly and is sealed with the pressure-containing assembly. The electric heating component 2 passes through the square flow channel and the pressure-bearing component simultaneously and is sealed and fixed with the pressure-bearing component. This embodiment solves the problems of electric heating, insulation and sealing by passing the electric heating assembly 2 through the square flow channel and the pressure-bearing assembly at the same time and sealing and fixing the pressure-bearing assembly, and realizes that the thermal-hydraulic characteristics are similar to those of the reactor fuel assembly. The low-voltage, high-power fuel assembly simulation process reduces the power consumption during simulation and simplifies...

Embodiment 2

[0032] like figure 1 As shown, on the basis of Embodiment 1, the pressure-bearing assembly includes an upper flange cover 4, an upper groove flange 6, a lower groove flange 11, and a lower flange cover 17, and the upper flange cover 4 is arranged on the upper The upper groove flange 6 is fixed to each other, the lower groove flange 11 is arranged above the lower flange cover 17 and fixed to each other, the upper groove flange 6 is arranged above the lower groove flange 11, and the upper groove flange 6 and A pressure-bearing cylinder 8 is arranged between the flanges 11 on the lower groove surface, and the pressure-bearing cylinder 8 is welded and fixed to the flange 6 on the upper groove surface and the flange 11 on the lower groove surface at the same time, and the square flow channel is arranged on the pressure-bearing cylinder 8 and both ends protrude from the upper groove surface flange 6 and the lower groove surface flange 11 respectively, the electric heating component ...

Embodiment 3

[0034] like figure 1 , figure 2 As shown, on the basis of the above embodiment, the electric heating assembly 2 includes an upper conductive copper head 19, an electric heating rod bundle and a lower conductive plate 23, the top of the electric heating rod bundle passes through the upper conductive copper head 19, and the bottom of the electric heating rod bundle passes through After passing through the square runner, it is fixed with the lower conductive plate 23, and the upper conductive copper head 19 is arranged between the upper flange cover 4 and the upper groove surface flange 6 and fixed with the upper groove surface flange 6, and the upper conductive copper head 19 The top end is set in the upper flange cover 4, the bottom end of the upper conductive copper head 19 is set in the upper groove surface flange 6, and the lower conductive plate 23 is arranged in the lower groove surface flange 11. The bottom end of the upper conductive copper head 19 is recessed into an ...

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Abstract

The invention discloses a low-voltage high-power pressurized water reactor fuel assembly simulation device, which comprises a pressure-bearing assembly, an electric heating assembly and a square flowchannel, wherein the square flow channel is arranged in the pressure-bearing assembly and is hermetically connected with the pressure-bearing assembly; and the electric heating assembly simultaneouslypasses through the square flow channel and the pressure-bearing assembly and is sealed with and fixed to the pressure-bearing assembly. The device meets requirements of a high-temperature and high-pressure experiment, keeps thermal hydraulic characteristic similarity with a reactor fuel assembly, can realize a simulation process of a low-voltage high-power pressurized water reactor fuel assembly,has low energy consumption, simplifies the structure, and is used for the critical heat flux and flow instability experiments of the pressurized water reactor fuel assembly so as to verify the thermal safety performance of a reactor.

Description

technical field [0001] The invention relates to a pressurized water reactor rod bundle fuel assembly simulation device, in particular to a low voltage and high power pressurized water reactor fuel assembly simulation device. Background technique [0002] A number of steady-state thermal design criteria are specified in the reactor design, including that the outer wall of the fuel element does not allow boiling criticality; in the steady-state rated conditions and expected transient operating conditions, no flow instability occurs . Therefore, in reactor design, critical heat flux and flow instability experiments need to be carried out to obtain critical heat flux values ​​and stable operating boundaries under different operating conditions to verify the thermal safety performance of the reactor. [0003] PWR fuel assemblies are generally composed of fuel rods with a diameter of 10mm arranged in a square of 15×15 or 17×17. The heat source is the energy generated by the fissi...

Claims

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Application Information

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IPC IPC(8): G21C17/00G06G7/54
CPCG06G7/54G21C17/001Y02E30/30
Inventor 昝元锋胡钰文黄彦平宫厚军
Owner NUCLEAR POWER INSTITUTE OF CHINA
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