Floating grid-based nuclear-thermal-mechanical multi-physical coupling calculation method

A calculation method and multi-physics technology, applied in calculation, computer-aided design, electrical digital data processing, etc., can solve the problems of reduced calculation accuracy of calculation amount and inability to fully reflect multi-physics state, and achieve the effect of improving calculation accuracy

Pending Publication Date: 2020-12-08
SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD
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Problems solved by technology

But at the same time, it is also noted that the results of a single design program cannot fully reflect the complex multi-physics state in the reactor, and the reduction in the amount of calculation comes from the simplification of the reactor physical model and the reduction of calculation accuracy

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  • Floating grid-based nuclear-thermal-mechanical multi-physical coupling calculation method
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[0015] In order to make the above objects, features and advantages of the present invention more comprehensible, the present invention will be further described in detail below in conjunction with the accompanying drawings and specific embodiments.

[0016] Next, the nuclear-thermal-mechanical multi-physics coupling calculation is performed for a typical fuel rod of a 1000MWe class nuclear power plant pressurized water reactor by using the method of the present invention.

[0017] The nuclear power of the reactor is 1000MWe, the system pressure is 15.5MPa, the coolant inlet flow rate is 15170kg / s, and the coolant inlet temperature is 290°C. There are 157 boxes of fuel assemblies in the reactor core, and there are 264 fuel rods in each box. This typical fuel rod is based on a square cell, using UO2 pellets, Zirlo zirconium alloy cladding, and filling the gap with helium. 426.72 cm.

[0018] For the above typical fuel rods, the specific steps to implement the nuclear-thermal-m...

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Abstract

The invention discloses a floating grid-based nuclear-thermal-mechanical multi-physical coupling calculation method. The method comprises the steps of establishing a fuel rod geometric model, carryingout a nuclear-thermal-force multi-physical iterative calculation process, carrying out plane heat transfer calculation, plane mechanics calculation and plane neutron transport calculation, and carrying out axial one-dimensional neutron diffusion calculation. According to the invention, neutronics, thermal hydraulic and mechanical problems are solved based on deformable floating grid coupling, andbehaviors of heat conduction, mechanical deformation, neutron transport, nuclide burnup and the like of a fuel rod in an extreme environment in a reactor are simulated; and meanwhile, multiple physical states such as temperature, stress, deformation, in-rod pressure, neutron group flux, power, burnup and isotope density of the fuel rod are obtained.

Description

technical field [0001] The invention belongs to the technical field of nuclear power numerical simulation, in particular to a technology for simulating the multi-physics coupling state of fuel rods in a reactor. Background technique [0002] The physical phenomena and physical processes produced by nuclear fuel rods under extreme conditions (high temperature, high pressure, strong irradiation) in the reactor are very complicated. Nevertheless, on the basis of phenomenological research, according to the research and understanding of fuel rod behavior and phenomena, the multi-physics problems of fuel rods can be attributed to heat transfer problems, mechanics problems, neutronics problems and chemical corrosion problems. Among them, because the change of chemical corrosion is very slow, the numerical simulation is more difficult, so it is not considered for the time being. Heat transfer problems study the temperature distribution of coolant and fuel rods, mechanical problems ...

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G06F30/20G06F30/23G06F119/08G06F119/14
CPCG06F30/20G06F30/23G06F2119/08G06F2119/14
Inventor 费敬然司胜义陈其昌杨波汤春桃毕光文彭良辉杨伟焱韩宇
Owner SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD
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