CN113609744B - Quick reactor core three-dimensional power construction method based on Meng Ka critical calculation single-step method - Google Patents
Quick reactor core three-dimensional power construction method based on Meng Ka critical calculation single-step method Download PDFInfo
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Abstract
According to the core three-dimensional power rapid construction method based on the Meng Ka critical calculation single-step method, by increasing the particle number generation by generation, the inactive generation is not calculated any more, the fission source convergence diagnosis problem is not considered, the critical calculation efficiency is remarkably improved Meng Ka in a manner of adjusting the weight of each calculation generation in real time, and all calculation generations are ensured to contribute to the calculation result. Based on the Meng Ka critical single-step method without the non-active generation, which is provided by the invention, the power distribution of the whole pile three-dimension can be quickly constructed, and the highest calculation efficiency is realized.
Description
Technical Field
The invention relates to a technology in the field of reactor physics, in particular to a technology for avoiding inactive generation by adjusting the particle number scale of Monte Care critical calculation, thereby improving the efficiency of Monte Care critical calculation and realizing the rapid construction of three-dimensional power of a reactor core.
Background
The three-dimensional power distribution of the reactor core is the most critical physical quantity in the research and development design of the novel reactor, and can be obtained through Meng Ka critical calculation, so the critical calculation is the most basic requirement of the physical design of the reactor. The traditional Meng Ka critical algorithm divides the computation process into inactive and active generations, namely: the stable convergent fission source distribution is obtained through the calculation of the inactive generation, and then the system information is counted through the calculation of the active generation. Wherein the computation of the inactive generation is not counted and is regarded as a waste of computing resources. In some large scale systems and loosely coupled systems, fission source convergence is slow, requiring hundreds of inactive generations of computation to be completed to achieve fission source convergence. Meanwhile, in the calculation process of the inactive generation, whether the fission source is converged is difficult to diagnose in real time, and calculation errors caused by starting statistics when the fission source is not converged are often avoided by adding the inactive generation, so that the waste of calculation resources is further caused. If the calculation efficiency is too low, the three-dimensional power distribution of the reactor core cannot be quickly constructed, so that the physical calculation of the reactor core with high fidelity is difficult, and the development and design of the novel reactor are faced with bottlenecks.
Disclosure of Invention
Aiming at the problem of low calculation efficiency caused by the inactive generation process of the conventional Meng Ka critical algorithm, the invention provides a method for quickly constructing three-dimensional power of a reactor core based on a Meng Ka critical calculation single-step method, wherein the calculation of the inactive generation is avoided by increasing the particle number generation by generation and adjusting the weight of each calculation generation in real time, so that the efficiency of critical calculation of Meng Ka can be obviously improved, the three-dimensional power distribution of the reactor core is quickly constructed, and the physical design of the reactor core of a novel reactor is effectively supported.
The invention is realized by the following technical scheme:
the invention relates to a method for quickly constructing three-dimensional power of a reactor core based on a Meng Ka critical calculation single-step method, which comprises the following steps:
step 1: determining an optimal sequence of particle number increments according to a fission source error propagation model: obtaining a universal particle number increasing sequence according to a fission source error transfer modelWherein: i represents the serial number of the calculation generation, and the values are 1, 2 and 3; m is m (1) Is the initial particle number, m (i) Is the particle number of the ith generation; c is a model dependent constant. By determining a constant c and an initial particle number m (1) An optimal sequence of particle count increments can be determined.
The present invention has demonstrated by mathematical derivation that c and m (1) The smaller the value of Meng Ka critical calculation single step method is, the higher the calculation efficiency is. In the invention, the constant c is preferably 1.0; initial particle number m (1) The larger the system or the higher the degree of loose coupling, the required initial particle count m, which is related to the system scale and the degree of loose coupling (1) The larger the value should be, the initial particle number m cannot be infinitely reduced to improve the calculation efficiency (1) Initial particle number m in the present invention (1) The preferred value is 50, 100 or 1000.
Step 2: and determining the optimal weight of each calculation generation to the whole calculation result according to the incremental sequence of the particle numbers. Because the prior p generation fission source has larger error, the optimal weighting coefficient is obtained by minimizing the proportion of the neutron statistical information of the prior p generation to the total neutron statistical information on the premise of fixed total particle number, thereby realizing the highest calculation efficiency.
The neutron statistical information of the previous generation accounts for the share of the total neutron statistical information Wherein: />Information amount of the previous generation p; s is(s) cum Is the total information quantity; n represents the total algebra of the simulation; w (w) (i) Is the weighting coefficient of the ith generation; m is m (i) Is the particle number of the ith generation; c is a model dependent constant.
The said processOptimizing weighting coefficients
Step 3: performing Meng Ka critical calculations and counting the three-dimensional power distribution of the core: ensuring that the particle number of each generation is equal to the optimal particle number increasing sequence, not distinguishing the inactive generation from the active generation, counting the power distribution from the 1 st calculation generation, and adopting an optimized weighting coefficient for each generation weight coefficient to further construct the three-dimensional power distribution of the reactor coreWherein: i is the sequence number of the calculation generation; w (w) (i) Is the weighting coefficient of the ith generation; m is m (i) Is the particle number of the ith generation; r (m) (i) ) Is the power response function of the ith generation, Q (i) Is the power distribution of the ith generation, N is the total calculated algebra.
Technical effects
The method integrally solves the problem of low calculation efficiency faced by the existing Meng Ka critical algorithm. According to the method, the inactive generation is not calculated any more, the problem of convergence diagnosis of the fission source is not considered, all calculation generations are guaranteed to contribute to the calculation result, and the effect of Meng Ka critical calculation is effectively improved. Based on the Meng Ka critical single-step method without the non-active generation, which is provided by the invention, the power distribution of the whole pile three-dimension can be quickly constructed, and the highest calculation efficiency is realized.
Drawings
FIG. 1 is a flow chart of the present invention;
FIG. 2 is a geometric view of an embodiment VERA reactor core;
fig. 3 is a three-dimensional power distribution diagram of an embodiment.
Detailed Description
As shown in fig. 2, a single-step application scenario of the Meng Ka critical computation without the non-active generation according to this embodiment, i.e., the VERA reactor core, is obtained by uniformly dividing the core into 15×15×10=2250 regions and using this method to calculate the power distribution of these 2250 regions, the power distribution of the core region is shown in fig. 3.
Firstly, using an RMC program to carry out physical modeling on the model, and defining geometric and material parameters of the model through an input card; a sequence of increasing particle numbers is selected for the computational model, namely input: m is m (1) C and h, and according to m (1) Determining the particle number sequence m by c and h (i) The method comprises the steps of carrying out a first treatment on the surface of the Determining a total algebra N to be calculated according to the total particle number; and carrying out mathematical optimization analysis on the whole model to determine the optimal weighting coefficient.
Starting from generation 1, neutron transport simulations were performed, with the neutrons of each generation of simulation satisfying a population increment sequence.
And counting the power distribution from the generation 1, wherein the counting process meets the requirement of a weighting technology.
After the N-generation calculation is completed, the data are analyzed and the result is processed, so that the three-dimensional power distribution of the whole pile is obtained.
In order to highlight the advantages of the present solution over the prior art, a comparative verification is performed here. 8 groups of calculation are carried out by adopting the traditional technical scheme, and the calculation parameters are as follows: (1) m=10,000, n 1 ＝100，n 2 ＝500；(2)m＝10，000，n 1 ＝200，n 2 ＝500；(3)m＝100，000，n 1 ＝100，n 2 ＝500；(4)m＝100，000，n 1 ＝200，n 2 ＝500；(5)m＝500，000，n 1 ＝100，n 2 ＝500；(6)m＝500，000，n 1 ＝200，n 2 ＝500；(7)m＝1，000，000，n 1 ＝100，n 2 ＝500；(8)m＝1，000，000，n 1 ＝200，n 2 =500. Where m represents the number of particles simulated per generation, n 1 =the number of inactive generations of the simulation, the total number of generations of the simulation.
Meanwhile, 8 groups of calculation are performed by using the calculation scheme, and the calculation parameters are as follows: (1) m is m 1 ＝50，c＝1.0，n＝1000；(2)m 1 ＝50，c＝1.0，n＝5000；(3)m 1 ＝50，c＝1.0，n＝10，000；(4)m 1 ＝100，c＝1.0，n＝100，000；(5)m 1 ＝100，c＝1.0，n＝1000；(6)m 1 ＝100，c＝1.0，n＝5000；(7)m 1 ＝100，c＝1.0，n＝10，000；(8)m 1 =100, c=1.0, n=100,000. M here 1 =initial number of particles, c represents a constant of the increasing sequence of the number of particles, n represents the number of calculated generations of the total simulation.
Measuring computational efficiency using a time-dependent average quality factor, the average quality factor Wherein: m is the number of statistical regions, T is the calculation time, re k Is the relative standard deviation of the kth region.
At the same time, the calculation efficiency is measured by using the average quality factor related to the particle number Wherein: m is the number of statistical regions, h is the simulated total particle count, re k Is the relative standard deviation of the kth region.
Two initial fission sources are set for critical calculations: (1) an initial point source at a central location of the VERA core; (2) a homogeneous body source over the full core of the VERA core. The calculation results are compared with table 1.
TABLE 1 comparison of the calculated average quality factors for each group
As can be seen from table 1 and fig. 3, the method can quickly construct the power distribution of the three-dimensional full core.
Compared with the prior art, the method has higher overall calculation efficiency. The efficiency of Meng Ka critical calculation can be effectively improved, so that three-dimensional power distribution of the reactor core can be quickly constructed, and the reactor core physical design of the novel reactor can be effectively supported.
The foregoing embodiments may be partially modified in numerous ways by those skilled in the art without departing from the principles and spirit of the invention, the scope of which is defined in the claims and not by the foregoing embodiments, and all such implementations are within the scope of the invention.
Claims (6)
1. The quick construction method for the three-dimensional power of the reactor core based on the Meng Ka critical calculation single-step method is characterized by comprising the following steps of:
step 1: determining an optimal sequence of particle number increments according to a fission source error propagation model: obtaining a universal particle number increasing sequence according to a fission source error transfer modelWherein: i represents the serial number of the calculation generation, and the values are 1, 2 and 3 …; m is m (1) Is the initial particle number, m (i) Is the particle number of the ith generation; c is a model-dependent constant, by determining the constant c and the initial particle number m (1) The optimal sequence of particle number increments can be determined;
step 2: determining the optimal weight of the whole calculation result of each calculation generation according to the incremental sequence of the particle numbers, and obtaining an optimal weighting coefficient by taking the share of the neutron statistical information of the previous generation with the total neutron statistical information of the previous generation as a target on the premise of fixed total particle numbers because of larger errors of the fission sources of the previous generation, thereby realizing the highest calculation efficiency;
step 3: performing Meng Ka critical calculations and counting the three-dimensional power distribution of the core: ensuring that the particle number of each generation is equal to the optimal particle number increasing sequence, not distinguishing the inactive generation from the active generation, counting the power distribution from the 1 st calculation generation, and adopting an optimized weighting coefficient for each generation weight coefficient to further construct the three-dimensional power distribution of the reactor coreWherein: i is the sequence number of the calculation generation; w (w) (i) Is the weighting coefficient of the ith generation; m is m (i) Is the particle number of the ith generation; r (m) (i) ) Is the power response function of the ith generation, Q (i) Is the power distribution of the ith generation, N is the total calculated algebra.
2. The method for quickly constructing the three-dimensional power of the reactor core based on the Meng Ka critical calculation single-step method, which is disclosed in claim 1, is characterized in that the non-active generation is not calculated any more, the fission source convergence diagnosis problem is not considered, and the statistics of the power distribution is carried out from the first generation.
3. The method for quickly constructing the three-dimensional power of the reactor core based on the Meng Ka critical calculation single-step method, which is disclosed in claim 1, is characterized in that the constant c takes a value of 1.0.
4. The method for rapidly constructing three-dimensional power of reactor core based on Meng Ka critical calculation single-step method as claimed in claim 1, wherein the initial particle number m (1) The value is 50, 100 or 1000.
5. The method for rapidly constructing three-dimensional power of reactor core based on Meng Ka critical calculation single-step method as claimed in claim 1, wherein the neutron statistical information of the previous p generations accounts for the share of the total neutron statistical information Wherein: />Information amount of the previous generation p; s is(s) cum Is the total information quantity; n represents the total algebra of the simulation; w (w) (i) Is the weighting coefficient of the ith generation; m is m (i) Is the particle number of the ith generation; c is a model dependent constant.
6. The method for quickly constructing three-dimensional power of reactor core based on Meng Ka critical calculation single-step method as set forth in claim 1 or 4, wherein the share of neutron statistics information of previous p generations with respect to total neutron statistics information is minimized as a target to obtain an optimized weighting coefficient on the premise of fixed total particle number,
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