Rod bundle channel visualization experiment body suitable for heating boiling conditions

Abstract

The invention provides a rod bundle channel visualization experiment body suitable for heating boiling conditions. The experiment body comprises a square quartz channel, an outlet and an inlet respectively disposed at the upper end and the lower end of the square quartz channel and a simulated fuel rod bundle disposed in the square quartz channel. The lower end of the simulated fuel rod bundle isconnected to the square quartz channel through a sealing flange. The experiment body is further provided with a positive conductive copper bar and a negative conductive copper bar, and the positive conductive copper bar is disposed at the upper end of the inlet of the body. The simulated fuel rod bundle includes a connecting copper head and a conductive copper rod and a stainless steel tube whichare arranged at the lower end of the connecting copper head. The conductive copper rod is disposed inside the stainless steel tube, and the outer surface of the conductive copper rod is provided withan insulating tube. The stainless steel tube is connected with the positive conductive copper bar, and the conductive copper rod is connected with the negative conductive copper bar. The experiment body solves the problem that the traditional wall temperature measurement method and a visualization experiment cannot be combined, can achieve measurement study of an inner flow field temperature fieldof the rod bundle channel under high temperature and two-phase conditions, and has the advantages of simple design and low cost.

Description

technical field [0001] The invention relates to a rod bundle channel visualization experiment body, in particular to a rod bundle channel visualization experiment body suitable for heating and boiling conditions, and belongs to the fields of fluid mechanics, heat transfer, reactor thermal hydraulics, nuclear safety and the like. Background technique [0002] The PWR core fuel assembly is an atypical rod bundle channel structure, and the fuel assembly is also equipped with a positioning grid, which leads to a more complicated fluid circulation structure in the fuel assembly, and further promotes the complex heat and mass transfer process in the fuel unit. for complex. During the normal operation of the reactor, the research on the steady-state flow heat transfer engineering in the bundle channel is very important for the economical efficiency of the reactor. Under accident conditions, especially under flow transient conditions, the flow in the bundle channel is prone to heat ...

AI Technical Summary

Problems solved by technology

However, due to the complex structure of the fuel assembly and the study of its internal flow and heat transfer behavior, scholars at home and abroad often use traditional thermocouples to measure the wall temperature of the rod bundle to predict the flow and heat transfer behavior in the rod bundle channel, and the measurement of the thermocouple can only Measuring the temperature of a single point or some points cannot obtain the detailed flow and heat transfer behavior in the fuel assembly, and the arrangement of thermocouples will inevitably have a certain impact on the internal behavior of the real fuel assembly, which will eventually lead to engineering problems. The real heat and mass transfer process in the component is still insufficiently understood, so a combination of advanced visual measurement and traditional measurement is required, but the combination of the two methods puts forward higher requirements for the design of the experimental Bent, the ontology needs to take into account The measurement requirements of traditional caloric technology and advanced visualization technology, so it is necessary to design a transparent body that can realize visual measurement even if it is heated to boiling with power supply, so as to realize the fine measurement of the flow and heat transfer behavior inside the rod bundle channel, thereby revealing the nuclear reactor fuel element. Heat transfer mechanism to improve the economics and safety of nuclear reactors

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