Migration path analysis method for steam bubbles generated by lead-based reactor accident

Abstract

The invention relates to a migration path analysis method for steam bubbles generated by a lead-based reactor accident. The method comprises the steps that 1, carrying out modeling according to reactor structure parameters, and inputting a primary loop initial temperature field, pressure field distribution, secondary loop temperature and pressure boundary conditions to serve as steady-state calculation initial values; 2, invoking a lead-based alloy physical relation, introducing a porous medium model and a turbulence Prandt model, and obtaining a steady-state temperature field and a pressure field of a primary loop of the reactor as initial values of accident condition calculation; 3, invoking a steam bubble drag force calculation function, and selecting a drag coefficient relational expression to calculate the drag force borne by the steam bubble; 4, invoking a relation of the quantity of the steam bubbles along with size distribution, and inputting a steam bubble quantity distribution rule at the initial moment of an accident; and 5, setting a crevasse position, and invoking an Euler-Lagrange algorithm to solve a steam bubble migration path until the path calculation is convergedand the migration duration meets the calculation requirement. The evaluation and guidance are provided for the design safety of the lead-based reactor and the judgment of the influence degree of thefracture accident of the steam generator heat transfer tube.

Description

technical field [0001] The invention relates to the field of serious accidents of lead-based reactors, in particular to a steam bubble migration path analysis method under a rupture accident of a heat transfer tube of a steam generator of a lead-based reactor. Background technique [0002] A lead-based reactor refers to a type of reactor that uses liquid metal lead or lead-secret alloy (collectively referred to as lead-based materials) as a coolant. The steam generator heat transfer tube rupture accident of lead-based reactor is the accident process in which the high-pressure water in the secondary circuit vaporizes and enters the core along with the flow of coolant in the primary circuit under the rupture condition of the steam generator heat transfer tube. Among them, the steam bubbles generated by the accident may be entrained and trapped in the core, which will cause positive cavitation reactivity in the local area of ​​the reactor core, which will lead to a surge in rea...

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Problems solved by technology

It can be seen that there is still a lack of theoretical research on steam bubble migration under steam generator heat transfer tube rupture accidents.

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