Method and equipment for solving physical response sensitivity of reactor

A response sensitivity and reactor technology, which is applied in the field of solving the physical response sensitivity of the reactor, can solve the problems of the increase of generalized neutron transport equations, the increase of calculation amount, the large amount of program code changes, etc., so as to achieve universality, portability, The effect of improving computational efficiency

Inactive Publication Date: 2021-05-11
NUCLEAR POWER INSTITUTE OF CHINA
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Problems solved by technology

This equation adds an orthogonal definite solution condition, and there is a negative source term, so the amount of changes to the program code is extremely large, and it is extremely difficult to implement in some mature commercial programs
In addition, if there are many responses to be analyzed and the number of generalized neutron transport equations to be solved increases, the computational complexity of this method will increase

Method used

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  • Method and equipment for solving physical response sensitivity of reactor
  • Method and equipment for solving physical response sensitivity of reactor
  • Method and equipment for solving physical response sensitivity of reactor

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0075] A method for solving the sensitivity of reactor physical response, the specific steps are:

[0076] Step 1. Sampling nuclear data based on covariance matrix decomposition;

[0077] The nuclear data is sampled by the following formula:

[0078]

[0079] in, Is a vector composed of n nuclear data, and satisfies the mean value Covariance matrix is ​​the multidimensional normal distribution of M; Obey the standard normal distribution N(0,1); U is a unitary matrix whose columns are M 2 Eigenvector of , M=UVU T ; V is a diagonal matrix, the value of its diagonal elements is Μ 2 The square root of the eigenvalue, V=V 1 / 2 V 1 / 2 .

[0080] Step 2: Obtain nuclear data samples with the sampling method in step 1, and further obtain the sensitivity of the generalized response to nuclear data through forward sensitivity analysis based on the reduced-order model.

[0081] The forward sensitivity analysis based on the reduced-order model is specifically as follows:

...

Embodiment 2

[0088] Based on the method provided in Example 1, the selected analysis object is the PWR cell TMI-1, which is composed of fuel elements, cladding, air gaps and moderators from the inside out ( figure 1 is a schematic diagram, and Table 1 is the specific calculation parameters). The calculation program selects the reactor core physical calculation program KYADJ. KYADJ uses the 45-group multi-group nuclear database as input. The calculation of neutron transport and conjugate neutron transport uses a two-dimensional one-dimensional coupling algorithm, which can be calculated effectively based on traditional perturbation theory. proliferation factor k eff Sensitivity to nuclear data.

[0089] Table 1 Main calculation parameters of TMI-1 cell

[0090]

[0091] Generalized Response Selection 235 The ratio of the fission to capture reaction rate of U, the analyzed nuclear data is 235 U fission cross-section, the nuclear data dimension is n=45, and the reduced-order model sele...

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Abstract

The invention discloses a method for solving the physical response sensitivity of a reactor. The method comprises the steps: firstly obtaining a sampling sample of multi-group nuclear data through covariance matrix decomposition and a multi-dimensional normal distribution sampling technology; and secondly, realizing a forward sensitivity analysis process based on a reduced-order model by using the sampling technology so as to obtain the sensitivity of the physical generalized response of the reactor to the nuclear data. According to the method for solving the physical response sensitivity of the reactor by using covariance matrix decomposition sampling provided by the invention, by combining the reduced-order model and the covariance matrix decomposition sampling technology, the complexity caused by using a generalized perturbation theory is completely avoided, meanwhile, the calculation amount of forward sensitivity analysis is effectively reduced, sensitivity with precision equivalent to that of a direct disturbance method is provided.

Description

technical field [0001] The invention relates to the technical field of nuclear reactor cores, in particular to a method and equipment for solving the sensitivity of the physical response of the reactor, which avoids the use of generalized perturbation theory, significantly reduces the calculation time of forward sensitivity analysis and improves efficiency while ensuring the accuracy of sensitivity. Background technique [0002] Sensitivity and uncertainty analysis of nuclear data has become an important content in reactor physical design. Among them, the sensitivity analysis of nuclear data refers to quantitatively describing the degree of influence of a certain nuclear data disturbance on the calculation results, which is measured by sensitivity. In practical applications, by analyzing the sensitivity of each nuclear data, we can focus on the important nuclear data, that is, the data with higher sensitivity. [0003] The commonly used methods for sensitivity analysis of n...

Claims

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Application Information

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IPC IPC(8): G06F30/20G06F17/16
CPCG06F30/20G06F17/16
Inventor 吴屈彭星杰于颖锐李庆赵文博刘琨吴文斌龚禾林
Owner NUCLEAR POWER INSTITUTE OF CHINA
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