A method for precise engineering of fusion reactor cladding

Abstract

The invention discloses a method applied to fusion reactor cladding accurate engineering design. The method comprises the following steps: firstly, performing plasma calculation to obtain anisotropicneutron source distribution and cladding first wall surface heat flux density distribution; combining anisotropic neutron source distribution obtained through plasma calculation in neutron transport physics calculation with material temperature distribution obtained through thermohydraulics calculation, and obtaining cladding core heat source distribution and cladding tritium propagation rate; obtaining material temperature distribution of different areas in the cladding by utilizing cladding first wall surface heat flux density distribution provided by plasma calculation and nuclear heat source distribution provided by neutron transport calculation in thermal hydraulics calculation; neutron transport calculation and thermal hydraulics calculation needing to be mutually iterated until therequirements of material temperature safe operation limitation and cladding tritium propagation rate are met. According to the method, engineering design can be carried out on the fusion reactor cladding in the real service environment of the cladding, the defect that in a traditional method, an isotropic neutron source and the surface heat flux of the first wall of the uniform cladding are adopted is overcome, and accurate engineering design of the cladding is achieved.

Description

technical field [0001] The invention relates to the technical field of cladding design of a fusion reactor, in particular to a method for precise engineering design of a cladding of a fusion reactor, and is a method for obtaining engineering design parameters of a cladding of a fusion reactor in a real service environment. Background technique [0002] The cladding is responsible for important functions such as energy conversion, tritium breeding, and radiation shielding in the fusion reactor. Among them, the coolant flows in a large number of parallel tubes to take away the heat in the cladding, and the neutron multiplier is used to increase the neutron flux to improve The tritium breeding ratio of the tritium breeder, and the fuel in the fusion reactor core is in a high-temperature (hundred million degrees) plasma state, which will have an important impact on the operating conditions of the cladding. During the operation of the plasma, a large number of neutrons and heat p...

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Problems solved by technology

[0004] These studies did not consider the influence of the high-temperature plasma of the fusion reactor core on the cladding, but only adopted the simple assumption of uniform heat flux and isotropic neutron source for the design and analysis of the cladding, which can only be applied to the cladding. In the conceptual design stage, it is difficult to realize the simulation of the real service environment of the fusion reactor cladding, and it is impossible to study the influence of the particles and heat pulses of the fusion core high-temperature plasma on the cladding operation, let alone meet the detailed engineering design requirements of the fusion reactor cladding

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