A Migration Path Analysis Method for Steam Bubbles Produced by Accidents in Lead-Based Reactors

Abstract

A method for analyzing the migration path of steam bubbles generated in a lead-based reactor accident. 1. Modeling is carried out according to the reactor structural parameters, and the initial temperature field and pressure field distribution of the primary loop are input, and the temperature and pressure boundary conditions of the secondary loop are used as initial values ​​for steady-state calculation ; 2. Call the physical property relational formula of lead-based alloy, introduce the porous media model and the turbulent Prandtl model, and obtain the steady-state temperature field and pressure field of the reactor primary circuit, and use it as the initial value for the calculation of the accident condition; 3. Call the steam bubble drag force calculation function, select the drag coefficient relational formula to calculate the drag force on the bubbles; 4. Call the relationship between the number of steam bubbles and the size distribution, and input the distribution law of the number of bubbles at the initial moment of the accident; 5. Set the location of the breach and call Euler-Lage The Langer algorithm solves the steam bubble migration path until the path calculation converges and the migration time meets the calculation requirements. The invention provides evaluation and guidance for the design safety of the lead-based reactor and the judgment of the impact degree of the rupture accident of the heat transfer tube of the steam generator.

Description

Technical field [0001] The present invention relates to the field of severe accidents of lead-based reactive reactors, and specific to a steam migration path analysis method under a heat transfer tube cracking accident of a lead-based reactor steam generator. Background technique [0002] The lead-based reactor refers to a type of reactor that is a coolant in a liquid metal lead or a lead-constituent (collective lead-based material). The steam generator of the lead-based reactor heat transfer tube rupture is under the cracking conditions of the steam generator heat transfer tube, and the second circuit high pressure water is vaporized and accompanying the flow of the flow of the coolant into the core of the core. Among them, the vapor bubbles generated by the accident may be entrained and stranded in the core, resulting in a positive aerosol reactivity of the local area of ​​the reactor core, thereby causing the reactive pile power surge to affect the safety of the reactor. There...

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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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