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A Method for Computing Axial Swelling Effect of Fast Neutron Stack Components

An axial swelling effect and component technology, which is applied in the field of core design and safety of nuclear reactors, can solve problems such as increasing the amount of calculation, difficulty in convergence of nodal flux, etc., and achieves the effect of improving calculation efficiency

Active Publication Date: 2018-11-09
XI AN JIAOTONG UNIV
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Problems solved by technology

[0004] Traditional methods of dealing with tine effects do not work well for axial swelling effects
First of all, the adaptive grid method will cause too fine grids in the core nodes, which not only greatly increases the calculation amount, but also makes it difficult for the node flux to converge
Calculating with the re-homogenization method requires the calculation of the homogenized cross-section for each node, which greatly increases the amount of calculation

Method used

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  • A Method for Computing Axial Swelling Effect of Fast Neutron Stack Components
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  • A Method for Computing Axial Swelling Effect of Fast Neutron Stack Components

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Embodiment Construction

[0018] Below in conjunction with accompanying drawing and specific embodiment the present invention is described in further detail:

[0019] The method of the present invention applies the variational nodal method based on non-uniform nodules to three-dimensional core calculation, separates the transport calculation grid from the burnup grid, and the transport calculation grid can contain different burnup Materials and burnup grids contain uniform materials, and the core block calculation method adopts the non-uniform variational block method, which can make the calculation blocks contain two types of burnup materials. After the calculation is completed, according to the flux expansion moment, the power distribution in the block in the axial direction can be obtained, so as to obtain the average flux in the burnup block, and then the cross section of the next burnup step can be obtained.

[0020] The whole calculation specifically includes the following steps:

[0021] Step 1...

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Abstract

A method for calculating the axial swelling effect of fast neutron reactor components, comprising the following steps: 1. Separate the transport calculation grid from the burnup calculation grid, the transport calculation grid remains unchanged throughout the calculation, and the fuel consumption calculation grid The consumption calculation grid keeps growing in the same proportion with the axial swelling of the fuel assembly; 2. Based on the variational block method, the weak form of the solution of the neutron transport equation is constructed, and the section in the block is a function related to the spatial position. A variety of materials are allowed inside the transport calculation block; 3. Use spherical harmonic functions and spatial orthogonal polynomials to expand the flux, and use the response matrix method to solve the flux expansion moment, so as to obtain the flux distribution of each block; 4 , Calculate the burnup depth of the burnup block according to the average power of the burnup block, obtain the uniform cross section of the burnup block according to the fuel consumption interpolation, and adjust the uniform cross section inside the burnup block according to the axial elongation of the component , and then obtain the required non-uniform section in the calculation node.

Description

technical field [0001] The invention relates to the technical field of nuclear reactor core design and safety, in particular to a method for calculating the axial swelling effect of fast neutron reactor components. Background technique [0002] Fast neutron reactors can convert fissile nuclides into fissile nuclides, greatly improving the utilization rate of uranium resources, which is of great significance to the sustainable development of nuclear energy. At present, fast reactors are still in the experimental and design stages, and accurate numerical simulations are essential for large-scale commercial use of fast reactors. [0003] Different from existing commercial pressurized water reactors, fast reactors usually use metal uranium-zirconium alloys as fuel in order to make the energy spectrum harder and obtain better breeding effects. Metal fuel has a large temperature expansion coefficient, and it is also prone to swelling and deformation when it is irradiated. In the...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G06F17/50
CPCG16Z99/00
Inventor 郑友琦李志鹏吴宏春李云召曹良志
Owner XI AN JIAOTONG UNIV
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