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Neutron transport calculation method for three-dimensional pressurized water reactor core

A technology for pressurized water reactors and cores, applied in the field of nuclear reactor core design and core safety calculations, to achieve both accuracy and efficiency, save time and money costs, and avoid grid waste

Active Publication Date: 2020-08-11
XI AN JIAOTONG UNIV
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Problems solved by technology

[0006] In order to overcome the problems existing in the above-mentioned prior art, the present invention provides a kind of neutron transport calculation method for three-dimensional pressurized water reactor core, and this method can be applied to the grid caused when the traditional characteristic line method simulates the whole core massive waste of resources

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  • Neutron transport calculation method for three-dimensional pressurized water reactor core
  • Neutron transport calculation method for three-dimensional pressurized water reactor core
  • Neutron transport calculation method for three-dimensional pressurized water reactor core

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Embodiment Construction

[0053] The present invention will be described in further detail below in conjunction with the accompanying drawings and specific embodiments.

[0054] Specific steps such as figure 1 As shown, the present invention divides the three-dimensional pressurized water reactor core to be simulated into two parts radially, and the specific steps are as follows:

[0055] Step 1: If figure 2 As shown, based on calculation requirements, PWR core geometry and material distribution, the PWR core is divided radially into two areas, simple area and complex area, which are the outer simple heavy-water light-water area and the inner complex area Core area, the internal complex area includes fuel area, control rods and conduits, coamings and grids, and core support structures;

[0056] Step 2: Read the geometry, material and boundary conditions of the two regions respectively;

[0057] Step 3: Based on the geometric information, material information and boundary condition information read ...

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Abstract

The invention discloses a neutron transport calculation method for a three-dimensional pressurized water reactor core, and the method comprises the steps: firstly dividing a reactor to be calculatedinto two regions in the radial direction, i.e., a region with a simple geometric material and a complex region; dividing grids on the simple region, establishing a neutron transport numerical model byusing a discrete longitudinal marking method, dividing a flat source area on the complex region, and establishing a neutron transport numerical model by using a characteristic line method; carrying out coupling calculation through the regional boundary until the result converges, and finally obtaining the characteristic value and neutron flux information of the reactor core. According to the method, the advantages of a characteristic line method and a discrete longitudinal marking method are combined, the requirement for fine construction of a complex region can be met, rapid calculation canbe conducted on a simple region, meanwhile, precision and efficiency are both considered, and time and money cost are saved for reactor numerical simulation.

Description

technical field [0001] The invention relates to the fields of nuclear reactor core design and core safety calculation, in particular to a neutron transport calculation method for a three-dimensional pressurized water reactor core. Background technique [0002] As a kind of clean energy, nuclear energy has incomparable advantages over traditional fossil energy, and it can be used as the main supply force of new energy for the follow-up development of our country. The nuclear reactor physical calculation analysis obtains the internal operating state of the reactor through numerical simulation, which is basically to solve the steady-state Boltzmann neutron transport equation. Among the mainstream methods are the discrete ordinate method (Sn) and the method of characteristic lines (MOC). [0003] The Sn method discretizes the continuous angular directions to obtain neutron transport equations at several angles, solve the equations to obtain the neutron angular flux in each dire...

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G06F30/20G06F111/10
CPCG06F30/20G06F2111/10
Inventor 刘宙宇张思凡曹良志吴宏春
Owner XI AN JIAOTONG UNIV
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