Method and equipment for solving burn-up calculation response sensitivity

A technology with response sensitivity and sensitivity, applied in the field of nuclear reactor core, can solve the problems of increasing equations to be solved, changing the source code of calculation programs, and difficult to implement, etc., to achieve the effect of easy portability and universality

Inactive Publication Date: 2021-04-09
NUCLEAR POWER INSTITUTE OF CHINA
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Problems solved by technology

However, this method needs to construct multiple generalized adjoint equations and burnup adjoint equations according to the type of response, and the source code of the reactor calculation program is greatly changed, which is extremely difficult to implement; once there are many burnup responses to be analyzed, the equations to be solved will also be increase, the computational cost also increases accordingly

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  • Method and equipment for solving burn-up calculation response sensitivity
  • Method and equipment for solving burn-up calculation response sensitivity
  • Method and equipment for solving burn-up calculation response sensitivity

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Embodiment 1

[0073]This embodiment provides a method of solving the combustion consumption calculation response sensitivity, and the specific steps are as follows:

[0074]Step 1, calculate the fuel consumption density curve of the nucleation:

[0075]During the calculation of the fuel consumption, the nuclear density after the operation of the nuclear data uncertainty causes the operation of transport fuel consumption, and is uncertain. The fuel consumption curve of the nucleation is represented as the fuel consumption, the change in nuclear density is uncertain. In order to calculate the fuel consumption density curve of the nucleus, the random disturbance of micro-cross section is completely fuel consumption calculation, and the amount of perturbation of the microscopic cross section during the calculation of the fuel consumption is maintained. Specifically, the number of sample sampling is designed, performing the complete fuel consumption calculation of the N-kind random disturbance micro-section...

Embodiment 2

[0118]This embodiment provides a method of solving the combustion consumption calculation sensitivity, and the specific operation steps are as follows:

[0119]This embodiment is based on the TMI-1 single-gate element example for fuel consumption calculation uncertainty analysis. Table 1 shows the fuel consumption time step of the TMI-1 single-gate element, and the combustion consumption is 10 steps. The power density is set to 25MW / THM. The fuel consumption of the fuel consumption is 10 GWD / THM. The program used to calculate the 2-D / 1-D coupled transport and the sub-group resonance method, and the Bikov solve the ignition method (CRAM) to form a complete resonance - transport - fuel consumption of fuel consumption calculation.

[0120]Table 1 TMI-1 single-gate element example fuel consumption time point (power density 25MW / THM)

[0121]

[0122]The nuclear data that needs to be analyzed234U,235U,236U,238U,237NP,238PU,239PU,240PU,241PU,242PU,241AM,243AM,242CM,243CM,244CM,245CM and246CM,...

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Abstract

The invention discloses a method and equipment for solving fuel consumption calculation response sensitivity, and the method can solve the sensitivity of calculation response of a transportation fuel consumption coupling program to nuclear data on the premise of not using a generalized perturbation theory. According to the method, the reduced-order model and forward sensitivity analysis are combined, and the sensitivity of all burn-up responses to all nuclear data can be obtained. Compared with a first-order perturbation theory, the method is simpler and more convenient to implement, has universality and is convenient to transplant to other reactor physical design programs.

Description

Technical field[0001]The present invention relates to the field of nuclear reactor cores, and more particularly to a method and apparatus for solving fuel consumption calculation sensitivity.Background technique[0002]The precise prediction of the combustion consumption of key physical parameters (response) has a vital role in the reaction of the reaction stack of fuel management, core design and safety. Due to the fact that the transport calculation and the fuel consumption calculation process exists more computational models, the response uncertainty analysis of transport and fuel consumption calculation is gradually become the hot problem of reactor safety analysis. Traditional reactor safety analysis reduces the economics of reactors due to lack of uncertainty analysis functions using conservative safety margins.[0003]In the uncertainty analysis of fuel consumption calculations, nuclear data is used as the basic input parameters, and the uncertainty of its introduction has become...

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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