Introduction
Since its advent in the 1950s, nuclear energy has been crucial for meeting the world’s energy needs and is an important component of clean energy. Nuclear energy is primarily generated through nuclear reactors, which are generally designed to operate for 30-40 years and can last even longer with license renewals. Data from the Power Reactor Information System indicates that among the total of 437 reactors, 289 reactors have been in operation for more than 30 years [1]. Thus, more than 60% of the current nuclear reactors face aging issues, which implies an increase in operational problems or anomalies in reactors. The aging of operational reactors also leads to increased mechanical vibrations of reactor internals, such as core barrels, control rods, in-core instruments, and fuel assemblies, or other vibrations such as flow blockage and coolant inlet perturbations [2-6].
Various reactor core monitoring techniques aim to address these challenges, and they are primarily based on observations of the neutron flux acquired by in-core and ex-core instrumentation combined with numerical simulations. These techniques and systems include CORTEX [7], BEACON [8], and RAINBOW [9]. A detailed overview of reactor core monitoring techniques is available in [10]. Field reconstruction combines observed data in the core and simulation data [11, 12] and aims to determine the neutronic field in the core. Subsequently, safety-related parameters are calculated, such as enthalpy rise hot channel factor, peak heat flux hot channel factor, linear power density of fuel rods, and deviation from nucleate boiling ratio.
Data assimilation is a key algorithm for field reconstruction, which originated from earth sciences, including meteorology and oceanography [13]. The data assimilation framework allows the combination of observations and models in an optimal and consistent manner, including information about their uncertainties [14-16]. It has been applied in several studies in nuclear engineering [9, 17-21] for field reconstruction in a unified formalism. Data assimilation with a reduced basis is another framework, which has been extensively researched in recent years [22-32]. In summary, studies on data assimilation have aimed to improve the accuracy, efficiency, and robustness of physical field reconstructions. Further details are available in Ref.[33].
However, as the location of the sensors affects the accuracy and robustness of the reconstructed field, optimization of sensor placement is an important aspect of the study. In [22], the authors proposed a generalized empirical interpolation method (GEIM) [34] to select quasi-optimal sensor locations in the framework of data assimilation and reduced basis, which was validated on three types of operational reactors at Électricité de France (EDF). In [35], simulated annealing was applied to optimize the placement of fixed in-core detectors using variance-based and information entropy-based methods to define the objective function. Recently, clustering methods, such as the K-means algorithm, have been used to optimize in-core detector locations for flux mapping in Advanced Heavy Water Reactor [36, 37]. In a recent study for building nuclear digital twins based on the Transient Reactor Test facility at the Idaho National Laboratory, a greedy algorithm was used to optimize sensor locations on a grid, adhering to user-defined constraints [38]. All these methods attempted to optimize the placement of the in-core detectors in a heuristic manner and were limited to a fixed sensor arrangement similar to that used during the training process. However, research on algorithms for handling detector vibrations is scanty.
The vibration of the in-core sensors near their nominal locations is a new problem that may arise from the aging of operational reactors. A typical limitation is attributed to the inability of all the aforementioned methods to handle spatially moving sensors. Recently, the work of [39] facilitated the practical use of neural networks for global field estimation, considering that sensors could move and become online or offline over time. The Voronoi tessellation [40] was used to obtain a structured-grid representation from sensor locations; subsequently, convolutional neural networks (CNNs) were used to build a map from movable sensors to the physical field. Inspired by this work, we adapted the framework to perform field reconstruction in nuclear reactors, such that the vibration of sensors was considered during the reconstruction of neutronic fields.
The remainder of this paper is organized as follows. In Sect. 2, we provide a detailed description of the methodology for field reconstruction with movable sensors by using Voronoi tessellation along with convolutional neural networks (V-CNN). In Sect. 3, we present the physical model and the detailed process for neutronic field reconstructing. secnumerical illustrates the numerical results, in which various error metrics have been presented to evaluate the performance of the method. Finally, we provide a brief conclusion and discuss future work in Sect. 5.
Methodology for field reconstruction with movable sensors
We aim to reconstruct a two-dimensional (2D) neutronic field
(i) a partition method using Voronoi tessellation which tolerated the local perturbations of sensor locations;
(ii) a machine learning framework that mapped the observations to the global physical field in the same structure.
We note that, considering that the sensors in the core of a reactor were fixed, such as self-powered neutron detectors (SPND), we only considered cases of sensor vibration near their fixed positions, rather than significant movement in the entire domain over time. The latter corresponds to the cases referred to in [39].
In Fig. 1, we present V-CNNs for neutronic field reconstruction and provide a detailed description of each component in the following sections.
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Voronoi tessellation for spatial domain partitions
For reconstruction using movable sensors, Voronoi tessellation is an essential step that maps the observations to the entire spatial domain. For a given space Ω, which is generally in 2D, a set of points
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Input and output of the machine learning model
To reconstruct the physical field using machine learning, we prepared the input data for the model using the following process:
(i) Determine the sensor locations
(ii) Calculate the Voronoi tessellation
(iii) Prepare the Voronoi mask field
The perturbations of sensor locations and its impact on the effectiveness of the network were also investigated in this study. The typical amplitude δ of the vibration of sensors in a reactor core is less than 1 cm [6], and we investigated the cases of δ= 1 cm, 3 cm, and 5 cm. The effects of the number and locations of sensors in these scenarios are described in the numerical results section.
To construct the training
Learning the map using convolutional neural networks
After preparing the input data for the model, a CNN model can be used to learn the map from observations to the field, in the same manner as handling images [44-46]. In this study, the channel of the CNN was set to one, and for each layer, the extraction of t key features of the input data through filtering operations was expressed as
Layers | Hidden | Filter size | Number of filters | Learning rate | Resolution |
---|---|---|---|---|---|
lmax | layers | H | m | of ADAM | nx × ny |
9 | 7 | 8 | 48 | 0.0001 | 171 × 171 |
The Voronoi mask field
Application to neutronic field reconstructions
Physical model
In this section, the reconstruction method for nuclear reactor cores is tested. We considered a typical benchmark in nuclear reactor physics, namely the 3D IAEA benchmark problem [51] prepared by the Computational Benchmark Problems Committee of the Mathematics and Computation Division of the American Nuclear Society. This benchmark was selected because it is adapted from realistic reactors, and its geometry and composition are much more complex than those of single-region or two-region problems. After completing this test, the method was directly tested based on real reactor calculations.
To test the algorithm, we used the 2D IAEA case, which represents the midplane z=190 cm of the 3D IAEA benchmark; see [51, page 437] for a detailed description. The 2D geometry of the reactor is shown in Fig. 3, where only one-quarter is shown because the rest can be inferred from the symmetry along the x and y axes. This quarter is denoted by Ω and comprises four subregions with different physical properties: the first three subregions form the core domain Ω1,2,3, while the fourth subregion is the reflector domain Ω4. Certain Newman boundary conditions are satisfied on the x and y axes considering symmetry, and the zero-boundary condition is satisfied on the external border, see Fig. 3.
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The neutron fields consist of fast and thermal fluxes, that is,
• Di: diffusion coefficient of group i with
•
•
•
• ν: average number of neutrons emitted per fission.
The axial buckling
Region | D1 (cm) | D2 (cm) | ∑1 → 2 (cm-1) | ∑a,1 (cm-1) | ∑a,2 (cm-1) | Material | ||
---|---|---|---|---|---|---|---|---|
Ω1 | 1.50 | 0.40 | 0.02 | 0.01 | 0.080 | 0.00 | 0.135 | Fuel 1 |
Ω2 | 1.50 | 0.40 | 0.02 | 0.01 | 0.085 | 0.00 | 0.135 | Fuel 2 |
Ω3 | 1.50 | 0.40 | 0.02 | 0.01 | 0.130 | 0.00 | 0.135 | Fuel 2 + Rod |
Ω4 | 2.00 | 0.30 | 0.04 | 0.00 | 0.010 | 0.00 | 0.000 | Reflector |
Under certain mild conditions of the parameters, the maximum eigenvalue λmax is real and strictly positive (see [54, Chapter XXI]). The associated eigenfunction ϕ, which is also real and positive at each point x, and is the flux of interest. In neutronics, the inverse of λmax is conventionally used and is called the multiplication factor
Field reconstruction
To simulate the variation in the neutronic fields with respect to the parameter variations, we considered the parameters in Sect. 2 as uncertain parameters. Specifically, we assumed the following:
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To synthesize the observations, we assumed that an in-core sensor was located at the center of each assembly to acquire the thermal flux. We further assumed that these sensors could move in a local square with a width δ cm, centered at the center of each assembly. We performed numerical tests for the cases δ = 1, 3, and 5 cm to investigate the effect of different levels of vibration of the sensors. Thus, observations were generated randomly from windows of width δ centered at their nominal locations (see Fig. 5). Then, the model
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Error metrics
Before presenting the numerical results, we define several metrics to evaluate the quality of the field reconstructions. The normalized root-mean-square residual of the difference between the reconstruction ør and test field øt is
Furthermore, the average assembly field (fluxes and power rate) and related errors were investigated. The average assembly power is defined as
Therefore, we introduce the structural similarity (SSIM) [56] index to measure the field reconstruction. In contrast to the general L2 error, the SSIM index measures similarity by comparing two images based on luminance, contrast, and structural similarity information.
Numerical results
We have described the methodology for field reconstruction with movable sensors using a CNN in Sect. 2 and presented a detailed process for neutronic field reconstruction based on a typical benchmark nuclear engineering domain in Sect. 3. In this section, we describe the numerical performance of the proposed method.
Performance for the benchmark problem
In Fig. 6, we present the error distributions of the reconstructed fields for different vibration amplitudes, namely, δ = 1,3, and 5 cm, for the 2D IAEA benchmark problem. The reconstruction of ø1 using observations from ø2 performs better than those of ø2 and P. Furthermore, the reconstruction error increases with the amplitude of the vibration, that is, when δ varies from 1 cm to 5 cm. The largest error appears around the interface of the fuel and reflector because of discontinuities in the materials, particularly for the fields of the thermal flux ø2 and the power rate P.
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The average assembly values of the reconstructed fluxes and power rate are shown in Fig. 7, and the same conclusions can be drawn. Because of the averaging process, the assembly exhibits considerably smaller relative errors than the pin-wise case.
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Three main conclusions can be drawn from analysis of the numerical results.
(i) The proposed V-CNN can reconstruct the multi-field using observations only from thermal flux;
(ii) The reconstruction errors for the assembly are significantly lower than 5%, which is acceptable for engineering applications, i.e., less than 10%, which is an acceptable criterion in reactor physics (more information is available in [57]);
(iii) Even with a movement of amplitude δ = 5 cm for the sensors, the proposed V-CNN reconstructs the field with an error less than 10%.
Average performance over a test set
To investigate the generalizability of the field reconstruction method, we analyzed the error performance for 1000 test samples. The error metrics were the average relative L2 error E(e2(ϕ)), average relative L∞ error
Table 3 illustrates the numerical results of the errors for the reconstruction of ø1 over the 1000 test samples. All error metrics exhibit good agreement between the reconstructed and original fields. The maximum errors, that is, the L∞ errors in both the pin-wise and assembly wise cases, are below 2%. The good performance is attributed to the smoothness of the fast flux owing to its relatively longer diffusion length than the thermal flux. Thus, the fast flux is less affected by the heterogeneity of the materials in this benchmark (Fig. 6a for example).
Width | 1 | 3 | 5 |
---|---|---|---|
E(e2(ø)) | 0.0097 | 0.0103 | 0.0119 |
STD(e2(ø)) | 0.0017 | 0.0020 | 0.0031 |
E(e∞(ø)) | 0.0276 | 0.0293 | 0.0303 |
0.0078 | 0.0090 | 0.0091 | |
0.0084 | 0.0094 | 0.0105 | |
0.0020 | 0.0022 | 0.0032 | |
0.0155 | 0.0159 | 0.0171 | |
0.0046 | 0.0054 | 0.0064 | |
0.9986 | 0.9982 | 0.9979 | |
0.0003 | 0.0004 | 0.0004 |
Tables 4 and 5 illustrate the numerical results of the errors for the reconstruction of ø2 and P over the 1000 test samples. The average L∞ errors in the pin-wise of the thermal flux and power rate were below 10% when the vibration amplitude was less than 3 cm. When the amplitude of the vibration increases, the average L∞ error exceeds 10%, which unsuitable for practical engineering applications. However,, the L∞ errors are much smaller for the assembly. The worst case occurs for δ = 5 cm when reconstructing ø2, which leads to an error of
Width | 1 | 3 | 5 |
---|---|---|---|
0.0167 | 0.0190 | 0.0213 | |
0.0025 | 0.0032 | 0.0041 | |
0.0751 | 0.1001 | 0.1219 | |
0.0197 | 0.0293 | 0.0391 | |
0.0120 | 0.0134 | 0.0141 | |
0.0025 | 0.0027 | 0.0028 | |
0.0216 | 0.0256 | 0.0288 | |
0.0085 | 0.0093 | 0.0109 | |
0.9969 | 0.9964 | 0.9957 | |
0.0006 | 0.0008 | 0.0010 |
Width | 1 | 3 | 5 |
---|---|---|---|
0.0137 | 0.0164 | 0.0253 | |
0.0031 | 0.0046 | 0.0060 | |
0.1429 | 0.2069 | 0.2640 | |
0.0811 | 0.1079 | 0.1119 | |
0.0097 | 0.0108 | 0.0192 | |
0.0027 | 0.0037 | 0.0058 | |
0.0182 | 0.0191 | 0.0257 | |
0.0069 | 0.0081 | 0.0082 | |
0.9951 | 0.9947 | 0.9920 | |
STD(SSIM(ø)) | 0.0012 | 0.0018 | 0.0023 |
Robustness analysis
The robustness of the reconstruction with respect to the number of observations nobs and amount of training data nsnapshot was examined. In Fig. 8, we show the dependence of the relative reconstruction errors in L2 norm and L∞ norm on nsnapshot = 128, 1280, 4096, 8192, 15743 and on nobs=25, 45, 81 to recover the thermal flux ϕ2 over the test set. The number of observations nobs=25, 45, and 81 correspond to sparsities of 0.0855%, 0.154%, and 0.277%, respectively, against the number of grid points in the field. The two figures demonstrate the robustness of the proposed method with respect to the sparsity of the sensors and training data. Few observations and training data lead to low-level reconstruction errors. Furthermore, the addition of training data improves the reconstruction accuracy more significantly than the addition of sensors. This result demonstrates that the proposed field reconstruction framework is robust against sensor failures and confirms its potential for practical applications.
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To investigate the robustness of the recovery with respect to the observation noise, a noise ϵσ that was randomly sampled in the range (-σ,σ) was added to each clean observation y, thereby generating a noisy observation yo=y(1+ϵσ) for each sensor. The dependence of the relative reconstruction errors in the L2 and L∞ norms of different noise levels, that is, σ=0.01,0.02,0.03,0.04,0.05 for recovering the thermal flux ϕ2 are shown in Table 6. The test was performed using 81 sensors with a vibration amplitude δ = 5 cm. The errors were first averaged over 100 repeated random observation samplings for each field reconstruction, and then averaged over the test set. On average, the reconstruction error changes significantly for noisy observations. The reconstruction error exhibits a slow linear growth trend with respect to the noise level. Although the L2 error is below 10%, which is satisfactory for nuclear engineering applications, the L∞ error remains at approximately 30%, which is unsatisfactory. This provides a direction for further research on reducing the L∞ error.
Noise level | E(e2(ϕ)) | E(e∞(ϕ)) |
---|---|---|
0.0 | 0.0213 | 0.1219 |
0.01 | 0.0493 | 0.2956 |
0.02 | 0.0510 | 0.2975 |
0.03 | 0.0536 | 0.3013 |
0.04 | 0.0572 | 0.3078 |
0.05 | 0.0616 | 0.3158 |
Conclusion
In this study, a V-CNN was proposed for neutronic field reconstruction to resolve the vibrations of in-core sensors, which may arise from the aging of operational reactors. Observations from movable in-core sensors were projected onto the same global field structure using Voronoi tessellation, holding the magnitude and location information of the sensors. General convolutional neural networks were used to learn maps from observations to the global field. Furthermore, the proposed method reconstructed multi-physics fields, including the fast flux, thermal flux, and power rate distributions, using observations from a single field, such as the thermal flux.
Numerical tests based on the IAEA benchmark demonstrated the efficiency of the proposed method. Three main conclusions can be drawn from the analysis of the numerical results.
(i) V-CNN can reconstruct the multi-field using observations only from thermal flux;
(ii) All the reconstruction errors in average are below 5%, which is satisfactory for engineering applications;
(iii) Even with a vibration amplitude of δ = 5 cm for sensors, V-CNN exhibits satisfactory performance.
In this study, the original CNN framework was used for image processing and was adapted for field reconstruction with rectangular mesh division. Field reconstruction with an irregular mesh requires additional mesh mapping to map the irregular mesh to a rectangular mesh. The adaptability of the proposed method to various reactor configurations is a continuation of this study.
This study provides a novel approach for field reconstruction using vibration sensors. Future work could highlight the uncertainty quantification of V-CNN considering observation noise systematically and proceed to practical engineering applications based on real nuclear reactors such as the HPR1000 reactor developed in China [58]. In this aspect, data uncertainty could be evaluated using a probabilistic neural network [59] or Bayesian neural network [60]in combination with V-CNN, while the epistemic uncertainty of the model could be examined using the Gaussian stochastic weight averaging technique [61] or other techniques.
To investigate the adaptability of the proposed method to an HPR1000 reactor, a pin-wise field calculation is necessary to consider the fuel and sensor vibrations, which is now being performed by our group. However, in practical engineering cases, the vibrations of reactor components, such as fuel and in-core sensors, lead to complex phenomena in the core. Many studies [2-6] have analyzed the induced variation of neutronic fields (also called neutron noise), considering the induced variation in the cross-section parameters of the neutron diffusion equations. Inspired by the neutron noise analysis process, a synthetic modeling approach is necessary for considering the effects of component vibrations. This approach is useful for clarifying the interplay or distinguish between field reconstructions using in-core sensor vibrations and general reactor noise analyses.
In addition, the combination of V-CNN and fault diagnosis [62] is a possible future research topic. With the development of machine learning in the field of nuclear physics [63, 64], the adoption of V-CNNs in nuclear physics, where CNNs are used [65-67], is also worth investigating.
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. Nuclear Science and Techniques 34, 79 (2023). https://doi.org/10.1007/s41365-023-01229-9The authors declare that they have no competing interests.