Experimentally runnable dynamic simulation model for pressurized water reactor and steam generator thereof

Abstract

The invention belongs to the technical field of nuclear power and particularly relates to a dynamic simulation model for a pressurized water reactor and a steam generator thereof, which can be used for conducting teaching experiments and simulating the normal operation and the loss-of-coolant accident of the pressurized water reactor. The dynamic simulation model consists of the steam generator, a pressure vessel, a pressure stabilizer, pipelines, a measurement system and a heating element. The lower head of the steam generator is divided into a water inlet chamber and a water outlet chamber through a baffle, wherein the water inlet chamber is connected with the upper part of the pressure vessel through a water inlet pipeline and the water outlet chamber is connected with the lower part of the pressure vessel through a water outlet pipeline. The water inlet pipeline is connected with the pressure stabilizer by arranging a bypass on the water inlet pipeline. The top of the pressure stabilizer is respectively connected with the tops of four liquid column manometers through the pipelines. The bottoms of the four liquid column manometers are respectively connected with four outlets which are evenly distributed on the side wall of the pressure vessel along the height direction. The model has the advantages that the structure is simple, the implementation is easy, the model not onlyis safe and reliable, but also can be operated by students in person, the perceptual and rational knowledge of the students to a nuclear reactor is improved and the goals of teaching and conducting scientific researches are achieved.

Description

technical field [0001] The invention belongs to the technical field of nuclear power energy, and in particular relates to a dynamic simulation model of a pressurized water reactor and a steam generator thereof capable of carrying out teaching experiments and simulating normal operation of the pressurized water reactor and loss of water accidents. Background technique [0002] The nuclear power plant is a huge system project. Due to the closed nature of the nuclear island, it is impossible to see the specific core structure even after arriving at the nuclear power plant. I have never seen a nuclear reactor after graduation. At present, most of the demonstration models used in nuclear power teaching to demonstrate the principles of nuclear reactors are static models made of plastic or foam, which can only show the composition of the equipment in the nuclear island, but cannot demonstrate the coolant flow process in the primary circuit, and the heat transfer of the primary and ...

AI Technical Summary

Problems solved by technology

[0003] The present invention aims at the shortcomings of the static model of the existing pressurized water reactor nuclear power plan

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