A Calculation Method for Thermal Neutron Scattering Effect of Silicon Carbide Coated Molten Salt Reactor

Abstract

The invention discloses a method for calculating the thermal neutron scattering effect of a silicon carbide coating molten salt reactor, which comprises the following steps: carrying out nuclear dataprocessing on the basis of the thermal neutron scattering rates of liquid molten salt, solid graphite and solid silicon carbide to obtain a thermal neutron scattering cross section library; calling athermal neutron scattering cross section library of liquid molten salt, solid graphite and solid silicon carbide, and carrying out assembly homogenization of the molten salt reactor by adopting a Monte Carlo neutron transport method to obtain homogenization group parameters of typical assemblies in the reactor core and near a reflecting layer; and calling few-group uniform parameters of typical components of the molten salt reactor, and calculating the influence of the thermal neutron scattering effect of the molten salt reactor on the key neutronics parameters of the molten salt reactor for the liquid fuel silicon carbide coating molten salt reactor on the basis of a neutron transport model or a neutron diffusion space-time kinetic model by considering the flow influence of the liquid molten salt. According to the method, the defect that a traditional deterministic theory method is difficult to completely adapt to the complex geometry of the molten salt reactor is overcome, and the obtained homogenization parameters of the molten salt reactor assembly are more accurate.

Description

technical field [0001] The present invention relates to the field of nuclear data and reactor physics, in particular to a new silicon carbide coated molten salt reactor, based on the two-step method from component to core to carry out the thermal neutron scattering effect on the key neutrons of silicon carbide coated molten salt reactor Calculation method of influence of scientific parameters. Background technique [0002] Whether it is a solid fuel molten salt reactor or a liquid fuel molten salt reactor, flowing liquid molten salt is used as the coolant. When the liquid molten salt flows through the graphite surface inside the molten salt reactor, the molten salt will permeate into the interior of the graphite. Hot spots form inside the graphite, raising the temperature of the graphite unacceptably and possibly even causing the graphite to break. [0003] In addition, in the thermal neutron scattering process in the thermal region, the thermal neutron scattering effect of...

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Problems solved by technology

[0004] The purpose of the present invention is to address the deficiencies in the prior art and provide a calculation method for the thermal neutron scattering effect of a silicon carbide coating molten salt reactor. The method applies the silicon carbide coating to the graphite in the liquid fuel molten salt reactor The surface of the moderator, or the silicon carbide coating is applied to the surface of the graphite-wrapped fuel balls in the solid fuel molten salt pile, thereby reducing the penetration of the flowing molten salt into the graphite, and overcoming the penetration zone of the molten salt into the graphite In addition, the Monte Carlo neutron transport method is used to calculate the homogenization parameters of molten salt reactor components, which overcomes the defect that the traditional deterministic method is difficult to fully apply to the complex geometry of molten salt reactors. , which avoids the loss of accuracy caused by geometric equivalence in the homogenization process of components based on the deterministic method, thus obtaining a more accurate group cross section, which is provided to the neutron transport based on the Green's function block method or neutron diffusion model, which can finally accurately calculate the influence of thermal neutron scattering effect of molten salt reactor neutron moderator material on the key neutronic parameters of molten salt reactor

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