A pressurized water reactor production isotope simulation method and system based on a pin-by-pin model

A pin-by-pin, analog method technology, applied in special data processing applications, instruments, electrical digital data processing, etc., can solve problems such as errors, inability to accurately consider the influence of reactor power, inaccurate neutron flux solutions, etc. , to achieve the effect of improving the calculation accuracy

CN109670239AActive Publication Date: 2019-04-23INST OF APPLIED PHYSICS & COMPUTATIONAL MATHEMATICS
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Patent Information

Authority / Receiving Office
CN · China
Patent Type
Applications(China)
Current Assignee / Owner
Publication Date
2019-04-23

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Abstract

The present invention provides a pressurized water reactor production isotope simulation method and system based on a pin-by-pin model. By establishing a geometry with the same geometric structure asa fuel rod and a target of each assembly in a reactor, the influence of the structure of the target piece on an activation calculation result is considered. Meanwhile, the calculation of the nuclide distribution of the target piece is combined with a transportation model, a thermal hydraulic model and a burnup model, so that the situation that the self-shielding effect of the target piece cannot be considered due to the fact that the target piece is calculated only through the burnup model at present and the influence of the target piece on the power and neutron flux of the area of the reactorafter absorbing neutrons are eliminated, and the calculation precision of the specific activity of the target piece is improved.
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Description

technical field

[0001] The invention relates to the technical field of isotope production, and more specifically, to a pressurized water reactor production isotope simulation method and system based on a pin-by-pin model. Background technique

[0002] Reactor, also known as nuclear reactor or atomic energy reactor, is a device that can maintain a controllable self-sustaining chain nuclear fission reaction to realize the utilization of nuclear energy. By rationally arranging the nuclear fuel in the reactor, the self-sustaining chain nuclear fission process can occur in it without the need for additional neutron sources. When a reactor is used to produce isotopes, a large amount of simulation calculation research on its engineering scheme is required, and the neutron flux at the location of the activated material (ie, the specific activity of the target) needs to be calculated. At present, the simulation calculation of the specific activity of the target is usually realized b...

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Embodiment Construction

[0072] The following will clearly and completely describe the technical solutions in the embodiments of the present invention with reference to the accompanying drawings in the embodiments of the present invention. Obviously, the described embodiments are only some, not all, embodiments of the present invention. Based on the embodiments of the present invention, all other embodiments obtained by persons of ordinary skill in the art without making creative efforts belong to the protection scope of the present invention.

[0073] The current method for calculating the target specific activity is mainly based on determinism and adopts a two-step method. First, the deterministic component program and core program are used to obtain the power history and neutron flux history of the location of the activated nuclide; The materials in the activated target are mixed and homogenized. Using the neutron flux history obtained in the first step as the initial condition, the burnup model is ...