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Prediction method for free liquid level fallback type entrainment of fast reactor sodium pool

A fast reactor sodium pool and prediction method technology, applied in the field of nuclear science and advanced reactor safety, can solve problems such as main pump cavitation, ultrasonic measurement equipment disturbance, etc., and achieve the effect of reducing calculation costs

Inactive Publication Date: 2021-09-03
XI AN JIAOTONG UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

The gas entrainment problem in the primary circuit of the sodium-cooled fast reactor may cause the accumulation of gas in the core or the gas passing through the core to cause safety problems, and may also cause other problems such as cavitation of the main pump and disturbance of ultrasonic measurement equipment

Method used

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  • Prediction method for free liquid level fallback type entrainment of fast reactor sodium pool
  • Prediction method for free liquid level fallback type entrainment of fast reactor sodium pool
  • Prediction method for free liquid level fallback type entrainment of fast reactor sodium pool

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Embodiment

[0051] by figure 1 The typical European sodium-cooled fast reactor is a computational reactor type. Using this method to predict the entrainment of the free liquid surface of the sodium pool, the steps are as follows:

[0052] Step 1: Obtain relevant parameters of the sodium-cooled fast reactor, including sodium pool structure and size parameters, sodium liquid level, sodium pool inlet pressure, sodium pool inlet sodium temperature, sodium pool inlet velocity, sodium density, sodium surface tension, sodium viscosity, etc.;

[0053] Step 2: Since the relatively large intermediate heat exchanger in the sodium pool has a blocking effect on the liquid sodium flowing out of the core, and the liquid sodium at this time has the maximum flow rate, it is selected to be formed by the control plug and the axis of the intermediate heat exchanger. The longitudinal plane of is used as the characteristic plane, such as figure 2 As shown, the area surrounded by the dotted line is the calcul...

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Abstract

The invention discloses a method for predicting free liquid level fallback type entrainment of a fast reactor sodium pool. The method comprises the following steps: 1, acquiring relevant parameters of a sodium-cooled fast reactor; 2, selecting a characteristic plane with the maximum flow velocity as a calculation area, and obtaining a two-dimensional geometric model through equal-proportion size reduction; 3, solving a control equation by using a computational fluid dynamics method in combination with the VOF multiphase flow model and the continuous surface tension model; 4, aiming at the model in the step 2, calculating entrainment occurrence conditions under different working conditions, and obtaining fallback parameters and judgment criteria under the current physical property; 5, fitting results to obtain a relation between a falling angle and a falling speed and a relation between the fallback speed and geometric parameters and an inlet speed under the current fluid physical property; and 6, calculating a fallback angle and a fallback speed of the predicted working condition under the current physical property, and predicting the occurrence condition of fallback type entrainment by using a judgment criterion. According to the method, the occurrence condition of falling entrainment of the sodium pool with the actual size under different working conditions can be directly predicted, and the method is provided for safety design and optimization of the sodium-cooled fast reactor.

Description

technical field [0001] The invention belongs to the field of nuclear science and technology, in particular to the field of safety of advanced reactors, and relates to a method for predicting entrainment of free liquid surface fall in a fast reactor sodium pool. [0002] technical background [0003] With the advancement of the construction of sodium-cooled fast reactors in the fourth-generation advanced reactor development plan, more and more safety issues are faced. The main thermal-hydraulic issues include components, cores, hot pools, cold pools, and decay heat dissipation. , gas entrainment, etc. The gas entrainment problem in the primary circuit of the sodium-cooled fast reactor may cause the accumulation of gas in the core or the gas passing through the core to cause safety problems, and may also cause other problems such as cavitation of the main pump and disturbance of ultrasonic measurement equipment. The falling entrainment of the free liquid surface of the sodium ...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G06F30/28G06Q10/04G06F113/08G06F119/14
CPCG06F30/28G06Q10/04G06F2113/08G06F2119/14
Inventor 巫英伟姚灏田文喜苏光辉秋穗正
Owner XI AN JIAOTONG UNIV