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Non-uniform electric heating nuclear fuel simulation rod

An electric heating and nuclear fuel technology, applied in the field of testing, can solve the problems of unsolved temperature measurement of electric heating rods, difficulty in ensuring the relative position of resistance wires and rods, low thermal efficiency, etc., and achieves rapid and large heat exchange, simple and compact structure design. , the effect of high safety

Pending Publication Date: 2018-04-20
CHONGQING UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

This solution does not solve the problem of measuring the wall surface temperature of the electric heating rod; the relative position between the resistance wire and the rod body is difficult to guarantee; the outer tube body is heated indirectly by energizing the resistance wire, and the thermal efficiency is low

Method used

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  • Non-uniform electric heating nuclear fuel simulation rod
  • Non-uniform electric heating nuclear fuel simulation rod

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0027] see figure 1 , a non-uniform electric heating nuclear fuel simulation rod is characterized in that: mainly comprising nickel rod 1, heating section 2, copper sheet 3, ceramic part 4, thermocouple 5, nickel tube 6, copper tube 7.

[0028] The nickel rod 1, the heating section 2, the nickel tube 6 and the copper tube 7 are sequentially connected from top to bottom to form a metal rod with a constant outer diameter. Its use environment can be high temperature and high pressure environment, and the working medium is deionized water.

[0029] The heating section 2 is a metal pipe with variable inner diameter. The upper end of the inner cavity of the heating section 2 is blocked by the nickel rod 1 , and the lower end of the inner cavity of the heating section 2 communicates with the inner cavity of the nickel tube 6 and the copper tube 7 .

[0030] The inner walls of the heating section 2 , the nickel tube 6 and the copper tube 7 have a ceramic layer, that is, a ceramic pi...

Embodiment 2

[0037] A critical heat flux test of a nuclear fuel assembly using the simulated rod described in Example 1 or a test of the thermal hydraulic performance of the fuel assembly.

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Abstract

The invention discloses a non-uniform electric heating nuclear fuel simulation rod and a test method thereof, and belongs to the field of reactor experimental research. The nuclear fuel simulation rodprovided by the invention is applied to critical heat flux density experimental research of nuclear fuel assemblies, and relates to the experimental research of thermal hydraulic performance of the fuel assemblies. The nuclear fuel simulation rod provided by the invention takes the situation that a current flows through a conductor to generate heat as the principle, and uses non-uniform heat generated along the axial direction of an electric heating rod to simulate non-uniform heat release along the axial direction of a nuclear fuel rod, so as to perform the critical heat flux density experimental research of the nuclear fuel assemblies.

Description

technical field [0001] The invention relates to the field of reactor test research, especially a test device and a test method using the test device. Background technique [0002] Critical heat flux is one of the key design parameters of nuclear fuel assemblies. At present, the critical heat flux of fuel assemblies cannot be predicted by theoretical methods, and can only be obtained through experiments. At the same time, nuclear fuel rods do not release heat uniformly along the axial direction, and the thermal environment at different axial heights is different. This factor must also be considered in the process of developing nuclear fuel assemblies. [0003] Prior to this application, there have been several devices for this test. For example, there is an electric heating rod reported in foreign literature, but the maximum working pressure of this device is only 40 bar, which is quite different from the actual pressure of the fuel assembly. This solution has not yet solve...

Claims

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Application Information

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IPC IPC(8): G21C17/00
CPCG21C17/001Y02E30/30
Inventor 文青龙
Owner CHONGQING UNIV
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