The method of simulating the transient problem of ads system by coupling monte carlo method
A Monte Carlo and transient technology, applied in the direction of instruments, complex mathematical operations, informatics, etc., can solve problems such as simulation instability and achieve the effect of improving accuracy
Active Publication Date: 2019-08-09
XI AN JIAOTONG UNIV
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[0010] In order to overcome the above-mentioned problems in the prior art, the object of the present invention is to provide a method for simulating the transient problem of the ADS system using the coupled Monte Carlo method, using the operation of transposing the matrix and constructing iterative acceleration to solve the problem of conjugate flux calculation and the problem of simulation instability at low subcriticality; compared with the transient calculation method of the fully deterministic theory, it has the advantages of high calculation accuracy, and at the same time solves the problem in the coupled Monte Carlo method; this method combines the dynamic part with The neutron transport part is externally coupled, which is convenient to use various Monte Carlo programs for replacement, and has versatility
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[0067] Below in conjunction with accompanying drawing and specific embodiment the present invention is described in further detail:
[0068] In the original deterministic estimation and correction quasi-static calculation method, the present invention couples the time-step neutron transport calculation in the transient analysis with the Monte Carlo method, and processes the conjugate by transposing the fission cross section and the scattering cross section For flux calculation, by introducing the fission source iteration factor, the Monte Carlo neutron simulation is accelerated and stabilized to achieve the desired effect.
[0069] Such as figure 1 Shown, the specific implementation steps of the present invention are as follows:
[0070] Step 1: The neutron spatiotemporal dynamics equation with delayed neutron precursor nuclei is processed by the improved quasi-static method of estimation and correction, and the complete estimation flux equation is obtained:
[0071]
[0...
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The invention discloses a method for simulating an ADS system transient problem by using a coupling Monte Carlo method. The method comprises the following steps: 1, using a forecasting calibration quasi-static method to obtain a forecast flux equation; 2, using a transposed matrix to calculate the adjoint flux at 0 moment; 3, introducing a fission source coefficient, and performing the iteration acceleration to solve the forecast flux equation; and 4, performing the adjoint flux normalization to the flux distribution obtained in the previous step so as to obtain the flux at the objective moment. The transposed matrix and the operation of constructing the iteration acceleration are used for solving the problems that the adjoint flux calculation and the simulation in the low subcritical degree are unstable. Compared with a transient computing method of a full certain theory, the method has the advantage of high calculation precision, and the problems in the coupling Monte Carlo method can be solved. The method is capable of externally coupling the dynamics part and the neutron transport part, and conveniently using each Monte Carlo procedure to replace, and has the universality.
Description
[0001] Technical field: [0002] The invention relates to the field of nuclear reactor design and reactor physical calculation, in particular to a method for simulating the transient problem of an ADS system by using a coupled Monte Carlo method. [0003] Background technique: [0004] Accelerator-driven subcritical reactor system (ADS) is a new type of nuclear energy reactor system. The accelerator generates high-energy proton flow, which bombards the spallation target to generate spallation neutrons, and acts as an external neutron source to drive the subcritical core to transmute the nuclear waste in it. . The system has the characteristics of high neutron flux density and hard energy spectrum. The reduction of the U / Pu nuclide loading proportion will lead to the decrease of the effective delayed neutron proportion of the core, and will also lead to the Doppler temperature feedback of the fuel. The effect is sharply attenuated, reducing the negative feedback mechanism durin...
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IPC IPC(8): G06F17/11
CPCG16Z99/00
Inventor 曹良志郑琪李云召赵传奇
Owner XI AN JIAOTONG UNIV