CN110991003B - Energy spectrum and scattering angle calculation method for initially-knocked-out atoms of nuclear material - Google Patents
Energy spectrum and scattering angle calculation method for initially-knocked-out atoms of nuclear material Download PDFInfo
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- 239000011824 nuclear material Substances 0.000 title claims abstract description 23
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- 238000011066 ex-situ storage Methods 0.000 claims description 6
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Abstract
The invention discloses a method for calculating an energy spectrum and a scattering angle of an initially-knocked atom of a nuclear material, which comprises the following steps of: (1) setting a neutron source model, and grouping neutron energy emitted by a neutron source; (2) extracting neutron information before and after collision; (3) elastic scattering and inelastic scattering are distinguished, and initial collision atom energy is calculated to obtain an energy spectrum; (4) and calculating a scattering angle to obtain a scattering angle distribution of the initial knocked-out atoms. The neutron source provided by the invention has various models and wide energy range, and can well analyze the neutron irradiation condition of nuclear materials in different types of reactors according to the obtained initial knock-out atomic energy spectrum and scattering angle.
Description
Technical Field
The invention relates to the field of nuclear energy science and engineering, in particular to a method for calculating an energy spectrum and a scattering angle of an initially-knocked atom of a nuclear material.
Background
Materials that serve as critical structures (e.g., cladding) within the reactor are often referred to as nuclear materials. Under the environment of strong irradiation in a reactor, cavities are easily generated in the nuclear material, and the whole nuclear material is subjected to swelling, deformation, cracking and the like, which possibly cause the change of potential safety hazards, so that the research on the irradiation resistance of the nuclear material is important for the safety of the nuclear reactor, as the material can be used as the material of an important structure in the reactor for a long time.
An important step in studying the radiation resistance of a nuclear material is to calculate the energy spectrum of its initial ejected atoms and the scatter angle distribution. After the material is irradiated, initial ejected atoms caused by collision of incident particles and material atoms are firstly generated, and then the initial ejected atoms carrying kinetic energy continue to generate cascade collision with other material atoms, so that the internal damage of the material is caused. In the case of low initial ejected atom energies (<200keV), the atomic dislocation damage of the material is mainly determined by the initial ejected atom energy. Therefore, the research on the initial knock-out atomic energy spectrum of the nuclear material has important significance on the research on the radiation resistance of the nuclear material. In addition, the movement direction of the initially knocked-out atoms has great influence on subsequent cascade effect, including collision times, transfer energy, movement paths and the like, so that the research on the scattering angle distribution of the initially knocked-out atoms is of great significance for the subsequent research on atom dislocation damage. Therefore, the method for calculating the energy spectrum and the scattering angle of the initially-knocked-out atom has important practical value.
Disclosure of Invention
The invention aims to provide a method for calculating an energy spectrum and a scattering angle of an initially-knocked-out atom of a nuclear material. The invention can analyze the performance of nuclear materials in different types of reactors under neutron irradiation.
The purpose of the invention can be realized by the following technical scheme:
a method for calculating an energy spectrum and a scattering angle of an initially ejected atom of a nuclear material comprises the following steps:
(1) setting a neutron source model, and grouping neutron energy emitted by a neutron source;
(2) extracting neutron information before and after collision;
(3) elastic scattering and inelastic scattering are distinguished, and initial collision atom energy is calculated to obtain an energy spectrum;
(4) and calculating a scattering angle to obtain a scattering angle distribution of the initial knocked-out atoms.
The nuclear material neutron source calculation model can reflect the irradiation degree of the nuclear material in the nuclear reactor, so that neutron collision data can be obtained. In order to be able to fully take into account the neutron irradiation of the nuclear material in different geometrical regions within the reactor, the neutron source may be a point source, a surface source or a source of the source.
In order to reflect the average energy of neutrons in different types of reactors (fast neutron spectrum reactors, intermediate energy neutron spectrum reactors and thermal neutron reactors), the neutron energy released by a neutron source is divided into multiple types. The energy released by the neutron source is set to be within the energy interval of 0.025eV to 10 MeV.
Specifically, in step (3), when the neutron energy after collision is less than the minimum energy corresponding to elastic collision, it is regarded as that inelastic scattering occurs; otherwise elastic scattering.
Further, when elastic scattering occurs:
Nx＝Nin-Nout-Ny (1)
wherein N isxRepresenting the energy of the primary ex-situ atom, NinFor incident neutron energy, NoutFor emission of neutron energy, NyIs the atom dislocation threshold energy.
Further, when inelastic scattering occurs:
Nx＝Nin-Nout-Ny-Nc (2)
wherein N isxRepresenting the energy of the primary ex-situ atom, NinFor incident neutron energy, NoutFor emission of neutron energy, NyIs an atom dislocation threshold energy, NcThe corresponding excited state energy of the target nucleus.
When the scattering angle is calculated, the momentum of the collided atoms can be deduced by using the momentum conservation theorem and combining the change of the neutron speed before and after collision, so that the scattering angle is calculated. In the present invention, the scattering angle is defined as the angle between the velocity direction of the ejected atoms and the velocity direction of the incident neutrons. The momentum in the u, v and w directions before and after collision obeys momentum conservation, the change amount of the neutron momentum before and after collision is the momentum obtained by initially knocking out the atoms, and the scattering angle of the initially knocked out atoms can be calculated after the momentum in the three directions of the initially knocked out atoms is obtained respectively.
The scattering angle is specifically calculated by the formula:
where arccos is an inverse cosine function, ix，jx，kxThe velocity components of the initial ejected atom in three directions, i, j and k are the velocity components of the incident neutron in three velocity directions, and theta is the included angle between the initial ejected atom and the incident direction of the neutron, namely the scattering angle of the initial ejected atom.
Compared with the prior art, the invention has the following beneficial effects:
the neutron source provided by the invention has various models and wide energy range, can better simulate the neutron irradiation conditions of nuclear materials in different geometric areas in a reactor, and can well analyze the neutron irradiation conditions of the nuclear materials in different types of reactors according to the obtained initial impact atomic energy spectrum and scattering angle.
Drawings
FIG. 1 is an energy distribution plot of initial knock-out atomic silicon (Si) of a silicon carbide cladding material under 1.5MeV neutron irradiation.
FIG. 2 is an energy distribution plot of initial knock-out atomic silicon (Si) of a silicon carbide cladding material under 1.5MeV neutron irradiation.
FIG. 3 is a graph of the scatter angle distribution of initially dislodged atomic carbon (C) and silicon (Si) from a silicon carbide cladding material under 1.5MeV neutron irradiation.
Detailed Description
The present invention will be described in further detail with reference to examples and drawings, but the present invention is not limited thereto.
Examples
A method for calculating an energy spectrum and a scattering angle of an initially ejected atom of a nuclear material comprises the following steps:
(1) setting a neutron source model, and grouping neutron energy emitted by a neutron source;
(2) extracting neutron information before and after collision;
(3) elastic scattering and inelastic scattering are distinguished, and initial collision atom energy is calculated to obtain an energy spectrum;
(4) and calculating a scattering angle to obtain a scattering angle distribution of the initial knocked-out atoms.
Regarding the setting of the neutron source model, in this embodiment, taking the cladding material of the nuclear fuel element as an example, a hollow cylindrical size model with a similar fuel element cladding is first set, and the hollow cylindrical size model has an outer diameter of 10.69mm, a height of 4387mm and a thickness of 0.49 mm. Considering that fast neutrons are generated by the fission reaction of solid nuclear fuel in the cladding, the neutron source is arranged in the hollow cylindrical model, and the selected neutron source is a solid cylindrical source with the radius of 4.81mm and the height of 4398 mm.
In this example, in order to reflect the average energy of neutrons in different types of reactors (fast neutron spectrum reactor, intermediate energy neutron spectrum reactor, thermal neutron reactor), the neutron energies emitted from the neutron source are totally divided into 10 groups, which are 0.025eV, 0.01MeV, 0.2MeV, 0.75MeV, 1.2MeV, 1.5MeV, 2.4MeV, 2.75MeV, 3.5MeV, and 10MeV, respectively.
In the embodiment, the DBCN card of the neutron transport simulation software MCNP5 is used for data acquisition. Each group selects 5000000 neutrons for tracking, and records the position, speed and energy of the neutrons when the neutrons enter and exit the grid cell surface or collide.
The present invention focuses on neutrons that collide with a target nucleic acid, and information fed back from these neutrons can be used to reversely infer the target nucleic acid that is expected to collide with. In the output file of the DBCN card, the whole process from generation to escape of a collided neutron is recorded, and when the collided neutron passes through a geometric plane and is collided, the DBCN card records the energy change of the neutron and the scattering angle of a target atom, and the states of the neutron before and after collision need to be studied, so that information of the neutron before and after collision needs to be extracted.
In this embodiment, in order to extract neutron information before and after a collision, a data screening program is written in Python language to screen an output file of the MCNP 5.
Since the digital format output by the DBCN card cannot be directly read by other software, for example, xx ± xx should be modified to xxE ± xx, so that the digital format can be read by data processing software such as Matlab, before the output file is imported into the data filtering program, preprocessing is required: and (4) intercepting the data of the DBCN card independently, and modifying the data expression mode output by the DBCN card.
And after the preprocessing is finished, the original data can be imported into the program. Since the file format output by the MCNP5 is a text file, when a Python program is imported for processing, the program is read and processed line by line in consideration of adapting to the array format of the processing data and performing a screening operation on the processing data. The previous line of data is firstly cached after a new line of data is read in, if the line recorded with the collision information is searched, the line and the cached content are respectively recorded into the two data, so that the collision information recorded each time can correspond to the information before the collision.
However, in actual operation, as the number of reading lines increases, the reading speed becomes slower and slower, and therefore, it is a method for increasing the processing speed to split the data contained in a large file into a plurality of smaller parts. To guarantee a certain reading speed, the split part must be small enough, the number must be enough, but as the number increases, a new problem is encountered, the memory allocated to the Python program by the system is not allowed to create too many arrays, otherwise, the memory overflows. In this case, the arrays are exported to the hard disk in the form of text files, and it is a feasible method to share the storage pressure of the memory with the hard disk, and it does not take much time to read data stored in the solid state disk with a faster reading speed. After the optimization, the processing speed is improved from seven hours per million neutrons to 30 minutes per million neutrons, and the processing speed is obviously improved.
After extraction, neutron information before and after each collision is obtained, including the position, speed and energy before and after the neutron collision, the type of target nuclei which the neutron collides with and the like, and the information is stored in two files respectively, corresponds to the information before and after the collision respectively, and corresponds to the information before and after the collision one by one according to the sequence.
Specifically, in step (3), when the neutron energy after collision is less than the minimum energy corresponding to elastic collision, it is regarded as that inelastic scattering occurs; otherwise elastic scattering.
Further, when elastic scattering occurs:
Nx＝Nin-Nout-Ny (1)
in the above formula, NxRepresenting the energy of the primary ex-situ atom, NinFor incident neutron energy, NoutFor emission of neutron energy, NyIs the atom dislocation threshold energy.
Further, when inelastic scattering occurs:
Nx＝Nin-Nout-Ny-Nc (2)
in the above formula, NxRepresenting the energy of the primary ex-situ atom, NinFor incident neutron energy, NoutFor emission of neutron energy, NyIs an atom dislocation threshold energy, NcThe corresponding excited state energy of the target nucleus.
When the scattering angle is calculated, the momentum of the collided atoms can be deduced by using the momentum conservation theorem and combining the change of the neutron speed before and after collision, so that the scattering angle is calculated. In the present invention, the scattering angle is defined as the angle between the velocity direction of the ejected atoms and the velocity direction of the incident neutrons. The momentum in the u, v and w directions before and after collision obeys momentum conservation, the change amount of the neutron momentum before and after collision is the momentum obtained by initially knocking out the atoms, and the scattering angle of the initially knocked out atoms can be calculated after the momentum in the three directions of the initially knocked out atoms is obtained respectively. The specific calculation formula is as follows:
in the above formula arccos is an inverse cosine function, ix，jx，kxThe velocity components of the initial ejected atom in three directions, i, j and k are the velocity components of the incident neutron in three velocity directions, and theta is the included angle between the initial ejected atom and the incident direction of the neutron, namely the scattering angle of the initial ejected atom.
So far, the energy spectrum (energy distribution) and the scattering angle of the initial ejected atoms of the nuclear material under the irradiation condition of incident neutrons with different energies are obtained. Based on the above calculation method, the energy distribution of the initial knock-out atomic carbon (C) of the silicon carbide cladding material under 1.5MeV neutron irradiation was obtained, as shown in fig. 1. The energy distribution of the initial knock-out atomic silicon (Si) of the silicon carbide cladding material under 1.5MeV neutron irradiation was obtained as shown in fig. 2. The scatter angle distribution of the silicon carbide cladding material initially knocked out atomic carbon (C) and silicon (Si) under 1.5MeV neutron irradiation was obtained as shown in fig. 3.
The above embodiments are preferred embodiments of the present invention, but the present invention is not limited to the above embodiments, and any other changes, modifications, substitutions, combinations, and simplifications which do not depart from the spirit and principle of the present invention should be construed as equivalents thereof, and all such changes, modifications, substitutions, combinations, and simplifications are intended to be included in the scope of the present invention.
Claims (4)
1. A method for calculating an energy spectrum and a scattering angle of an initially ejected atom of a nuclear material is characterized by comprising the following steps of:
(1) setting a neutron source model, and grouping neutron energy emitted by a neutron source;
(2) extracting neutron information before and after collision;
(3) elastic scattering and inelastic scattering are distinguished, and initial collision atom energy is calculated;
(4) calculating a scattering angle to obtain a scattering angle distribution of the initial collided atoms;
in the step (3), when the neutron energy after collision is less than the minimum energy corresponding to elastic collision, the neutron energy is regarded as the occurrence of inelastic scattering; otherwise, elastic scattering;
when elastic scattering occurs:
Nx＝Nin-Nout-Ny (1)
wherein N isxRepresenting the energy of the primary ex-situ atom, NinFor incident neutron energy, NoutFor emission of neutron energy, NyIs atomic dislocation threshold energy;
when inelastic scattering occurs:
Nx＝Nin-Nout-Ny-Nc (2)
wherein N isxRepresenting the energy of the primary ex-situ atom, NinFor incident neutron energy, NoutFor emission of neutron energy, NyIs an atom dislocation threshold energy, NcThe corresponding excited state energy of the target nucleus.
2. The method of claim 1, wherein the neutron source is a point source, a surface source, or a source.
3. The method of claim 1, wherein in step (1), the energy released by the neutron source is set to be within an energy interval of 0.025eV to 10MeV, and the energy released by the neutron source is grouped according to the average energy of neutrons within different types of reactors.
4. The calculation method according to claim 1, wherein the scattering angle is specifically calculated by the formula:
where arccos is an inverse cosine function, ix，jx，kxThe velocity components of the initial ejected atom in three directions, i, j and k are the velocity components of the incident neutron in three velocity directions, and theta is the included angle between the initial ejected atom and the incident direction of the neutron, namely the scattering angle of the initial ejected atom.
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| CN107247286A (en) * | 2017-05-16 | 2017-10-13 | 北京大学 | A kind of fast neutron spectrum measuring system and method |
| CN108426898A (en) * | 2018-02-24 | 2018-08-21 | 中国工程物理研究院材料研究所 | The method that heavy nucleus material is quickly identified using cosmic ray μ |
| CN108717479A (en) * | 2018-04-27 | 2018-10-30 | 西安交通大学 | A kind of neutron dynamics weighting Monte Carlo of Continuous Energy |
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| CN107247286A (en) * | 2017-05-16 | 2017-10-13 | 北京大学 | A kind of fast neutron spectrum measuring system and method |
| CN108426898A (en) * | 2018-02-24 | 2018-08-21 | 中国工程物理研究院材料研究所 | The method that heavy nucleus material is quickly identified using cosmic ray μ |
| CN108717479A (en) * | 2018-04-27 | 2018-10-30 | 西安交通大学 | A kind of neutron dynamics weighting Monte Carlo of Continuous Energy |
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