Fused salt reactor tritium transportation characteristic coupling calculation method

Abstract

The invention discloses a fused salt reactor tritium transportation characteristic coupling calculation method. The method mainly comprises the following steps: 1, obtaining geometric parameters, operation parameters and program calculation parameters of a fused salt reactor; 2, calculating an adsorption capacity limit value of graphite to tritium; 3, calculating the generation amount of tritium and the graphite adsorption amount at the reactor core; 4, calculating the corrosion amount of tritium to chromium at the heat pipe section and the deposition amount of chromium ions; 5, calcuating thecorrosion amount of tritium to chromium, the deposition amount of chromium ions and the tritium gas permeation amount at the heat exchanger; 6, calculating the corrosion amount of tritium to chromiumat the cold pipe section and the deposition amount of chromium ions; And 7, if the current time is equal to the steady-state operation time of the molten salt reactor, outputting a calculation result, otherwise, returning to the step 2, and performing calculation again until the calculation is finished. According to the method, the production of tritium in the molten salt reactor, transportationcharacteristics such as graphite adsorption, corrosion / deposition and permeation, and the influence of neutron irradiation on the graphite adsorption capacity are considered, so that the production amount, the adsorption amount and the permeation amount of tritium in the molten salt reactor can be obtained, and a reference is provided for radiation protection of the molten salt reactor.

Description

technical field [0001] The invention relates to the field of nuclear reactor safety, in particular to a coupling calculation method for tritium transport characteristics of molten salt reactors. Background technique [0002] Tritium (T) is an intrinsic product of molten salt reactors, Li in FLiBe + After reacting with neutrons, a large amount of tritium is produced, and these tritiums are mainly formed as tritium fluoride (TF) and tritium gas (T 2 ) form, they have strong corrosion and strong diffusion and penetration ability respectively. Tritium has a long half-life (12.43 years), and it will diffuse and migrate with the flow of high-temperature molten salt, causing corrosion and radiation damage to metal pipelines, affecting the mechanical properties and service life of materials. to T 2 Tritium in the form of tritium has strong permeability in most metals and alloy materials. It can split into tritium atoms on the surface of the material and enter the material, which ...

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Problems solved by technology

However, the fluorine-salt-cooled high-temperature reactor has only been proposed for more than ten years, and the overall research is still in the stage of conceptual design, basic theory and experimental research, and many key technical issues and basic safety review methods have yet to be explored and studied

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