A control method for simulating the neutron reactivity feedback process of a nuclear reactor based on a thermal-hydraulic experimental device for simulating the neutron reactivity feedback process of a nuclear reactor

Abstract

The invention provides a thermal hydraulic experiment device and method for simulating a nuclear reactor neutron reactivity feedback process. The thermal hydraulic experiment device comprises an electric heating experiment section, a shell-tube type cooler, a voltage stabilizer, a pressurizing nitrogen gas tank, a circulating pump, a cooling water pump, a cooling water tank, a cooling water tower, a pipeline, a valve, a measuring instrument, a data acquisition system, a control computer, a high-frequency direct-current power supply and a conductive copper bar. The high-frequency direct-current power supply is used for electrifying the electric heating experiment section. The circulating pump is connected with an inlet of the electric heating experiment section through a pipeline; the circulating pump is provided with a bypass pipeline; an outlet of the electric heating experiment section is connected with a pipe side inlet of the shell-tube type cooler through a pipeline. A control system for simulating nuclear reactor neutron reactivity is additionally arranged on the thermal hydraulic experiment device, and can be used for simulating the reactivity feedback process and a thermal hydraulic response process of nuclear reactors under various instant working conditions; the thermal hydraulic experiment device has the advantage of simulating various types of experiment working conditions, which are not easy to carry out in the nuclear reactor, under a nuclear-radiation-free environment.

Description

technical field [0001] The invention relates to a thermohydraulic experimental device and a control method for experimentally simulating the neutron reactivity feedback process of a nuclear reactor. Background technique [0002] In nuclear reactors, there is a feedback coupling effect between reactivity and fuel temperature, coolant temperature, core coolant void fraction, especially in natural circulation reactors, coolant circulation flow is also affected by core power and coolant temperature , and its coupling effect is more complex. Therefore, the nuclear reactor reactivity feedback process has important engineering significance for the safe operation of nuclear reactors. [0003] At present, most of the research literature on the reactivity feedback process of nuclear reactors is theoretical calculation research, and there are few researches using experimental simulation methods in the open literature. In the article "Stability Experiment of Low Pressure Natural Circu...

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Problems solved by technology

In the article "Stability Experiment of Low Pressure Natural Circulation Two-Phase Flow under Density Kernel Feedback Conditions", the measured coolant density is used as the input parameter, and the heating power is controlled by the neutron dynamics results, and the natural circulation under different working conditions is studied. The stability of two-phase flow, but this literature only considers the reactivity feedback effect brought by the change of coolant density, and does not consider the very important effects of fuel temperature reactivity feedback in the reactor; the literature "Experimental study of natural circulation instability with void reactivityfeedback during startup transients for a BWR-type SMR" and "Start-up transienttest simulation with and without void-reactivity feedback for a two-phase natural circulation reactor", the void reactivity feedback on boiling water was considered on the natural circulation experimental loop The influence of the transient process of reactor start-up, but the important influence of fuel temperature reactivity feedback and coolant temperature reactivity feedback on reactor thermal-hydraulic characteristics is not considered; the literature "Reactivity insertion limits in a typical pool-type research reactor cooled by natural circulation In ", the neutron dynamics model was used to calculate the reactivity input limit of the 10MW IAEAMTR reactor and the response of various important parameters of the reactor after the reactivity input was applied, but no experimental verification was designed.

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