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Neutron dynamical weighted Monte Carlo calculation method for continuous energy

A neutron dynamics and Monte Carlo technology, applied in the field of neutron dynamics weighted Monte Carlo calculation, can solve the problems that the impact cannot be evaluated or eliminated, and achieve the effect of facilitating the physical process, facilitating the analysis, and improving the applicability

Inactive Publication Date: 2018-10-30
XI AN JIAOTONG UNIV
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Problems solved by technology

As the most reliable method currently recognized, if the Monte Carlo dynamics method cannot give the neutron dynamics parameters that change finely with time, then the influence of these approximations in the deterministic dynamics method on the calculation results cannot be evaluated , irremovable

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  • Neutron dynamical weighted Monte Carlo calculation method for continuous energy
  • Neutron dynamical weighted Monte Carlo calculation method for continuous energy
  • Neutron dynamical weighted Monte Carlo calculation method for continuous energy

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Embodiment Construction

[0021] Below in conjunction with accompanying drawing and specific embodiment the present invention is described in further detail:

[0022] Such as figure 1 Shown, the neutron dynamics weighted Monte Carlo calculation method of a kind of continuous energy of the present invention, the steps are as follows:

[0023] Step 1: The user sets the restart switch in the input according to the actual situation; if the restart switch is turned on, the initial particle information provided by the user is read into the initial particle source library; if the restart switch is turned off, all the initial particle information Both are regarded as neutrons, and the distribution information of the initial particles is extracted according to the user's requirements to establish the initial particle source library; after the initial particle source library is established, the initial particles are taken out from the source library for simulation; if the initial particles are neutrons , then g...

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Abstract

The invention discloses a neutron dynamical weighted Monte Carlo calculation method for continuous energy, and relates to a continuous energy weighted Monte Carlo dynamical method. According to the method, a time dimensionality and an energy dimensionality are imported in the particle simulation process so as to really simulate random walk processes, on space and time, of neutrons; when neutron collisions are processed, a concept of weights is imported to simplify the conditions after nuclear reaction of neutrons; in order to obtain a correct physical quantity or neutron dynamical parameter ona certain time and then obtain exquisite change of the physical quantity of neutron dynamical parameter along with the time, distribution, on energy, of neutrons, namely, a neutron energy spectrum, is detailedly considered and the neutron energy spectrum is convoluted with other parameters; and the applicability, precision and calculation efficiency of a Monte Carlo method in neutron dynamical calculation can be improved, physical quantities, such as neutron dynamical parameters and power, and exquisitely changing along with the time can be obtained by utilizing the Monte Carlo method, so that convenience is brought to analyze the physical processes and mathematical models.

Description

technical field [0001] The invention relates to the fields of nuclear reactor design and reactor physics calculation, in particular to a continuous energy neutron dynamics weighted Monte Carlo calculation method. Background technique [0002] Monte Carlo method is a method widely used in reactor physical analysis and calculation. In systems described by steady-state neutron transport equations, that is, systems in which physical quantities do not change with time, the solution obtained by this method is usually regarded as a reference solution. Compared with the deterministic method, the Monte Carlo method has its unique advantages in the determination of errors, the increase in the amount of calculation for multidimensional problems, and the accuracy. [0003] During the expected safety assessment of the reactor and the actual operation of the reactor, physical quantities such as neutron flux often change with time. This kind of problem is called a transient problem, and ...

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Application Information

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IPC IPC(8): G06F17/50
CPCG06F30/20G06F2119/06
Inventor 李云召李捷吴宏春曹良志郑友琦刘宙宇祖铁军
Owner XI AN JIAOTONG UNIV
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