Method for simulating natural circulation flow characteristics of nuclear reactor fluid

Abstract

The invention discloses a method for simulating the natural circulation flow characteristics of nuclear reactor fluid, aiming at solving the problems that a simple way of reducing the power scale and reducing the system size is adopted, so that fluid flow and heat transfer characteristics in a reactor core and a steam generator are greatly different from the actual characteristics, and the natural cycle characteristics can not be the accurately simulated. The method comprises the steps of acquiring a simulation ratio of the main parameters of an experimental device and a prototype reactor system according to the criteria number of simulating single-phase natural circulation and on the basis of a limiting condition of the criteria number of the experimental device being the same as that of the prototype reactor system; setting the experimental device according to the simulation ratio so as to obtain the natural circulation characteristics which are the same as the natural circulation characteristics of the prototype reactor system. The method can be used for accurately simulating the natural circulation capability of the reactor core in real time after the accident of a nuclear reactor happens as well as the variation rule of the parameters which are closely related with the safety of the reactor based on a small-scale experimental size proportion.

Description

technical field [0001] The invention relates to a method capable of simulating the single-phase natural circulation flow characteristics of a nuclear reactor system, in particular to a method for simulating the natural circulation flow characteristics of a nuclear reactor fluid. Background technique [0002] When an accident occurs in a nuclear reactor, the control rods are quickly inserted into the core, triggering an emergency shutdown. After a nuclear reactor shutdown, although the sustainable chain fission reactor in the core is suspended, the decay of fission products in the core fuel elements continues to generate heat, namely core decay heat. In order to prevent the core decay heat from damaging the fuel elements, it is still necessary to effectively cool the core under accident conditions to protect the safety of the reactor. It is an important direction for the design and development of advanced nuclear reactors to establish a natural circulation flow in the core i...

AI Technical Summary

Problems solved by technology

[0004] The technical problem to be solved by the present invention is: the power and geometric dimensions of existing nuclear reactors make it impossible to carry out full-scale experimental research and verification in most cases. The fluid flow and heat transfer characteristics in the core and steam generator are quite different from the actual characteristics, and the accurate simulation of the natural circulation characteristics cannot be carried out; the purpose of the present invention is to provide a method for simulating the natural circulation flow characteristics of nuclear reactor fluids, It can simulate in real time and accurately the natural circulation capability of the nuclear reactor core after an accident with a small-scale experimental scale, as well as the changing rules of parameters closely related to reactor safety, providing important technical support for the design and development of advanced nuclear reactors

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