Method for calculating breakage rate of core fuel element coated particles of pebble-bed high-temperature gas cooled reactor

Abstract

The invention relates to a pebble-bed high-temperature gas cooled reactor core fuel element coated particle damage rate calculation method, and belongs to the technical field of reactor engineering, and the method comprises the following steps: S1, calculating the stock of a short-life inert gas fission nuclide core disc; s2, a Booth diffusion release model is used, and the release rate / generation rate of the short-life inert gas fission nuclide is obtained according to the temperature of the fuel element; s3, calculating a theoretical calculation expression of the fission nuclide activity concentration of the short-life inert gas of the primary loop by using the primary loop nuclide migration model; s4, obtaining an experimental measurement value of the fission nuclide activity concentration of the primary loop short-life inert gas at the sampling moment through gas sampling measurement; and S5, according to a theoretical calculation expression and an experimental measurement value, optimally solving a core fuel element coating particle damage rate and a matrix graphite uranium pollution share. According to the invention, reactor core fuel element performance and state key parameters required by radiation safety research, source item calculation, accident analysis and the like of the pebble-bed high-temperature gas cooled reactor can be obtained.

Description

technical field [0001] The invention belongs to the technical field of reactor engineering, in particular to a method for calculating the damage rate of cladding particles of a pebble bed type high temperature gas-cooled reactor core fuel element. Background technique [0002] High Temperature Gas-cooled Reactor (HTGR) is the prototype reactor of Very High Temperature Reactor (VHTR), which has the safety features of the fourth generation advanced nuclear reactor. The modular pebble bed type high temperature gas-cooled reactor uses helium as the coolant, graphite as the moderator, and the reactor core outlet temperature is 700-1000 °C. An important feature of the modular pebble bed type high-temperature gas-cooled reactor is high temperature: the core outlet temperature reaches 700-1000 °C. All have broad application prospects. [0003] Inherent safety is another important feature of the modular pebble bed type high temperature gas-cooled reactor. The core of its technology...

AI Technical Summary

Problems solved by technology

[0008] At present, there is no mature method in the world to calculate the damage rate of the core fuel element coating particles of the modular pebble bed high-temperature gas-cooled reactor and the method of uranium pollution.

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