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Visualization experiment system of core melt fragmentation behavior during severe accident of sodium-cooled fast reactor

A serious accident, sodium-cooled fast reactor technology, applied in the field of nuclear energy, can solve the problems of the diameter and shape control of the liquid column that cannot be released from the melt, the omission of key information of the melt and the coolant, the dead angle of the camera, etc., to avoid installation and operation. It becomes too complicated, guarantees reference value, and studies the effect of comprehensive parameters

Active Publication Date: 2021-12-31
SUN YAT SEN UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

For the melt release part, this invention does not introduce a pressurized heat supplementary tube, and it is impossible to accurately control the melt release rate by accurately adjusting the pressure in the furnace
Although this invention can realize the analysis of variables such as melt release height, melt temperature and water temperature, it cannot control variables such as the diameter and shape of the melt release liquid column.
At the same time, since it can only be observed from four specific windows, its camera may have dead angles, thus missing some key information about the interaction process between the melt and the coolant
In addition, the fragmentation product collector in this invention can only collect and analyze the fragments as a whole, but cannot collect them in different regions, and cannot further measure and analyze the properties of local fragments, which seriously restricts the understanding of the fragmentation process and mechanism of the melt

Method used

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  • Visualization experiment system of core melt fragmentation behavior during severe accident of sodium-cooled fast reactor
  • Visualization experiment system of core melt fragmentation behavior during severe accident of sodium-cooled fast reactor
  • Visualization experiment system of core melt fragmentation behavior during severe accident of sodium-cooled fast reactor

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Experimental program
Comparison scheme
Effect test

Embodiment 1

[0031] Such as figure 1 , 2 , 3, the visualized experimental system for the fragmentation behavior of the core melt when the sodium-cooled fast reactor serious accident provided by the present invention includes a support 2, a temperature-controllable annular resistance wire heating furnace 1 arranged on the support 2, a top The first high-temperature melt pneumatic valve 3 connected to the bottom of the temperature-controllable annular resistance wire heating furnace 1, the top and the bottom of the first high-temperature melt pneumatic valve 3 are connected to the pressurized heating pipe 4, the top is connected to the bottom of the pressurized heat supply pipe 4 The connected second high-temperature melt pneumatic valve 5, the visualization experiment container 6 arranged below the second high-temperature melt pneumatic valve 5 and the crushed product collector 9 arranged in the visualization experiment container 6, the visualization experiment container 6 adopts Made of t...

Embodiment 2

[0034] In this embodiment, the stent 2 of Embodiment 1 is specifically defined, as figure 1 As shown, the bracket 2 provided in this embodiment is a stainless steel structure, and a climbable ladder structure is designed on both sides, and the bracket 2 is designed to be detachable.

Embodiment 3

[0036] This embodiment limits the optimization scheme of the visualization experiment system of embodiment 1 and embodiment 2, such as figure 1 , 3 As shown, on the basis of Embodiment 1 and Embodiment 2, the experimental system provided by this embodiment also includes a control terminal 7, the control terminal 7 and the temperature-controllable annular resistance wire heating furnace 1, the first high-temperature melt pneumatic The valve 3, the pressurized heat supplement pipe 4, the second high-temperature melt pneumatic valve 5 are electrically connected to the heating module of the visualization experiment vessel. Through the control terminal 7, the opening and closing of the temperature-controllable annular resistance wire heating furnace 1, the first high-temperature melt pneumatic valve 3, the pressurized heating pipe 4, the second high-temperature melt pneumatic valve 5, and the heating function of the visualization experiment container can be realized. No, so as to ...

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Abstract

The invention relates to a visual experiment system for the fragmentation behavior of the reactor core melt during a severe accident of a sodium-cooled fast reactor, comprising a support, a temperature-controllable annular resistance wire heating furnace arranged on the support, a top and a temperature-controllable annular resistance The first high-temperature melt pneumatic valve connected to the bottom of the wire heating furnace, the pressurized heating pipe connected to the top of the first high-temperature melt pneumatic valve, and the second high-temperature melt pneumatic valve connected to the bottom of the pressurized heat-supplementary pipe are set at The visualization experiment container under the second high temperature melt pneumatic valve and the crushed product collector arranged in the visualization experiment container, the visualization experiment container is made of transparent material.

Description

technical field [0001] The invention relates to the technical field of nuclear energy, and more particularly relates to a visual experiment system for the fragmentation behavior of core molten material during a serious accident of a sodium-cooled fast reactor. Background technique [0002] Compared with the second-generation and third-generation reactors, the fourth-generation nuclear energy system is an advanced nuclear energy system with higher safety, stronger economic competitiveness, less nuclear waste and effective prevention of nuclear proliferation. The "Generation IV Nuclear Energy System International Forum (GIF)" established in 2001 selected six types of the most promising Generation IV reactor types, among which the sodium-cooled fast reactor has good breeding characteristics and the most abundant construction and operating experience, has become the "No. 1 seed player" in the fourth-generation nuclear energy system in the world. Although the probability of a se...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21C17/00
CPCG21C17/001Y02E30/30
Inventor 成松柏何利观王健源朱芳萌
Owner SUN YAT SEN UNIV
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