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Reactor thermal-hydraulic simulation testing apparatus and fluid dynamics characteristic simulation method

A simulation test, thermal hydraulic technology, applied in reactors, nuclear reactor monitoring, nuclear engineering, etc., can solve the problems of cumbersome process and affecting the efficiency of simulation tests, and achieve the effect of simple overall structure, low cost and easy realization

Active Publication Date: 2017-01-18
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

When the existing reactor thermal-hydraulic system simulation test device is applied, the process of adjusting the fluid dynamic characteristics to be consistent with the prototype is relatively cumbersome, which seriously affects the test efficiency of the simulation test

Method used

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  • Reactor thermal-hydraulic simulation testing apparatus and fluid dynamics characteristic simulation method
  • Reactor thermal-hydraulic simulation testing apparatus and fluid dynamics characteristic simulation method
  • Reactor thermal-hydraulic simulation testing apparatus and fluid dynamics characteristic simulation method

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Embodiment 1

[0039] Such as figure 1 As shown, the reactor thermal-hydraulic simulation test device includes a reactor simulation body 1, a steam generator simulation body 3, and a main circulation pump 6. The inlet and outlet of the steam generator simulation body 3 are connected to the reactor simulation body 1 outlet and The inlet of the main circulating pump 6 is connected, and the outlet of the main circulating pump 6 is connected to the inlet of the reactor simulation body 1 through a pipeline. In this embodiment, the pipe between the inlet of the steam generator simulation body 3 and the outlet of the reactor simulation body 1 is provided with a hot section resistance regulator 2, and the pipe between the outlet of the steam generator simulation body 3 and the inlet of the main circulation pump 6 is provided There are a cold section resistance adjusting member 4 and a check valve 5, and the check valve 5 is located between the cold section resistance adjusting member 4 and the main ci...

Embodiment 2

[0067] This embodiment makes the following further restrictions on the basis of embodiment 1: This embodiment also includes a hot-end pressure difference transmitter 9, a cold-end pressure difference transmitter 10, and a pumping pressure difference transmitter 11. , Both the positive pressure ends of the hot section pressure difference transmitter 9 and the pump path pressure difference transmitter 11 are connected with the pipeline between the pump path resistance adjusting member 7 and the Venturi flowmeter 8, and the hot section pressure difference is transmitted Both the negative pressure ends of the cold section pressure difference transmitter 9 and the cold section pressure difference transmitter 10 are connected to the pipeline between the hot section resistance adjusting member 2 and the steam generator simulation body 3. The cold section pressure difference transmitter 10 has a positive pressure end and The negative pressure end of the pump path differential pressure t...

Embodiment 3

[0069] In order to facilitate adjustment of the reference pressure of the reactor simulation body 1, this embodiment further defines the following on the basis of Embodiment 1 or Embodiment 2: This embodiment also includes a regulator 12, wherein the regulator 12 and the reactor The outlet of the simulation body 1 is turned on.

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Abstract

The invention discloses a reactor thermal-hydraulic simulation testing apparatus which comprises a reactorsimulation body, a vapor generator simulation body and a main circulating pump. The inlet and the outlet of the vapor generator simulation body are communicated with the outlet of the reactorsimulation body and the inlet of the main circulating pump, and the outlet of the main circulating pump is communicated with the inlet of the reactorsimulation body. A heat-section resistance adjusting part is arranged on the pipeline between the inlet of the vapor generator simulation body and the outlet of the reactorsimulation body, a cold-section resistance adjusting part and a stop valve are arranged on the pipeline between the outlet of the vapor generator simulation body and the inlet of the main circulating pump, and a pump way resistance adjusting part and a Venturi flowmeter are arranged on the pipeline between the outlet of the main circulating pump and the inlet of the reactorsimulation body. The invention further discloses a fluid dynamics characteristic simulation method based on the reactor thermal-hydraulic simulation testing apparatus. During application, fluid dynamics characteristics are adjusted to be consistent to a reactor prototype for implementation, and the testing efficiency of a simulation test can be improved.

Description

Technical field [0001] The invention relates to the technical field of reactor thermal hydraulics and safety, in particular to a reactor thermal hydraulic simulation test device and a fluid dynamic characteristic simulation method. Background technique [0002] In the existing large-scale nuclear power plants or nuclear power plants, the scale of various thermal systems is huge, and it is difficult to carry out tests by means of full-scale simulation. Therefore, a system simulation test device that scales the prototype according to certain simulation criteria is often used to study the thermal and hydraulic characteristics of the reactor system. Commonly used simulation criteria include geometrical similarity criteria, dynamics similarity criteria, and related dimensionless criteria. The application of dynamics similarity criteria must ensure that the simulation test device is consistent with the fluid dynamics of the prototype. Since the simulation test device is different from...

Claims

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Application Information

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IPC IPC(8): G21C17/00G21C17/017
CPCG21C17/001G21C17/017Y02E30/30
Inventor 唐瑜黄彦平徐建军谢添舟谭曙时彭兴建
Owner NUCLEAR POWER INSTITUTE OF CHINA
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