Review of Fourth-Order Predictive Modeling and Illustrative Application to a Nuclear Reactor Benchmark. I. Typical High-Order Sensitivity and Uncertainty Analysis
Abstract
:1. Introduction
2. Model Sensitivity and Uncertainty Analysis Input for the Fourth-Order Maximum Entropy Based Predictive Modeling Methodology (4th-BERRU-PM): Review and Applicability to Energy Systems
2.1. Input to the 4th-BERRU-PM Methodology: 4th-Order Sensitivity and Uncertainty Analysis of Model Responses to Model Parameters
- (i)
- The expected value, denoted as , of a computed response , for ; the vector of the computed responses is defined as follows: . Up to, and including, the fourth-order response sensitivities to parameters, the expected value of a computed response has the following expression obtained by formally integrating Equation (1) over the unknown distribution of parameters:In Equation (2), the moments up to and including the fourth-order of the unknown distribution of model parameters are assumed to be known. These moments are as follows: (a) the covariances of two model parameters, and , are denoted as , , where denotes the total number of parameters under consideration; the parameter covariance matrix is denoted as ; (b) the triple-correlations of three model parameters , , and , are denoted as , where ; (c) the quadruple-correlations of four model parameters , , , and , are denoted as , where .
- (ii)
- The correlation, denoted as , between a parameter and a computed response , for and ; the correlation matrix between parameters and computed responses is denoted as . Up to, and including, the fourth-order response sensitivities to parameters, the correlation between a parameter and a computed response has the following expression:
- (iii)
- The covariances, denoted as , between two computed responses and , for ; the covariance matrix of computed responses is denoted as . Up to and including the fourth-order response sensitivities to parameters, the covariance between two computed responses has the following expression:
- (iv)
- The triple correlations among three responses, , and , , which are denoted as . Up to and including the fourth-order response sensitivities to parameters, these triple correlations among three responses have the following expression:
- (v)
- The quadruple-correlations among four responses, , , and , for , which are denoted as . Up to and including the fourth-order response sensitivities to parameters, these quadruple correlations among computed responses have the following expression:
- (vi)
- The expressions of the triple and quadruple correlations among parameters and responses are provided in Ref. [12]; they will not be reproduced here because they are considered to be negligible by comparison to the other terms used within the 4th-BERRU-PM methodology.
2.2. Applicability of the 4th-Order Sensitivity and Uncertainty Analysis to Energy Systems
3. Illustrative High-Order Uncertainty Analysis of the PERP Reactor Physics Benchmark
3.1. “High Precision” Parameters, Having Uniform Relative Standard Deviations
3.2. “Medium Precision” Parameters, Having Uniform Relative Standard Deviations
3.3. “Low Precision” Parameters, Having Uniform Relative Standard Deviations
4. Concluding Remarks
Author Contributions
Funding
Data Availability Statement
Conflicts of Interest
Appendix A. Computational Model of the PERP Benchmark
Materials | Isotopes | Weight Fraction | Density (g/cm3) | Zones |
---|---|---|---|---|
Material 1 (plutonium metal) | Isotope 1 (239Pu) | 9.3804 × 10−1 | 19.6 | Material 1 is assigned to zone 1, which has a radius of 3.794 cm. |
Isotope 2 (240Pu) | 5.9411 × 10−2 | |||
Isotope 3 (69Ga) | 1.5152 × 10−3 | |||
Isotope 4 (71Ga) | 1.0346 × 10−3 | |||
Material 2 (polyethylene) | Isotope 5 (12C) | 8.5630 × 10−1 | 0.95 | Material 2 is assigned to zone 2, which has an inner radius of 3.794 cm and an outer radius of 7.604 cm. |
Isotope 6 (1H) | 1.4370 × 10−1 |
g | 1 | 2 | 3 | 4 | 5 | 6 |
1.50 × 101 | 1.35 × 101 | 1.20 × 101 | 1.00 × 101 | 7.79 × 100 | 6.07 × 100 | |
1.70 × 101 | 1.50 × 101 | 1.35 × 101 | 1.20 × 101 | 1.00 × 101 | 7.79 × 100 | |
g | 7 | 8 | 9 | 10 | 11 | 12 |
3.68 × 100 | 2.87 × 100 | 2.23 × 100 | 1.74 × 100 | 1.35 × 100 | 8.23 × 10−1 | |
6.07 × 100 | 3.68 × 100 | 2.87 × 100 | 2.23 × 100 | 1.74 × 100 | 1.35 × 100 | |
g | 13 | 14 | 15 | 16 | 17 | 18 |
5.00 × 10−1 | 3.03 × 10−1 | 1.84 × 10−1 | 6.76 × 10−2 | 2.48 × 10−2 | 9.12 × 10−3 | |
8.23 × 10−1 | 5.00 × 10−1 | 3.03 × 10−1 | 1.84 × 10−1 | 6.76 × 10−2 | 2.48 × 10−2 | |
g | 19 | 20 | 21 | 22 | 23 | 24 |
3.35 × 10−3 | 1.24 × 10−3 | 4.54 × 10−4 | 1.67 × 10−4 | 6.14 × 10−5 | 2.26 × 10−5 | |
9.12 × 10−3 | 3.35 × 10−3 | 1.24 × 10−3 | 4.54 × 10−4 | 1.67 × 10−4 | 6.14 × 10−5 | |
g | 25 | 26 | 27 | 28 | 29 | 30 |
8.32 × 10−6 | 3.06 × 10−6 | 1.13 × 10−6 | 4.14 × 10−7 | 1.52 × 10−7 | 1.39 × 10−10 | |
2.26 × 10−5 | 8.32 × 10−6 | 3.06 × 10−6 | 1.13 × 10−6 | 4.14 × 10−7 | 1.52 × 10−7 |
- Using the notation employed in PARTISN [17], the quantity denotes the “group-flux” for group , and is the unknown state-function obtained by solving Equations (A1) and (A2).
- The spontaneous-fission isotopes in the PERP benchmark are “isotope 1” (239Pu) and “isotope 2” (240Pu). The quantity denotes the total number of spontaneous-fission isotopes; for the PERP benchmark, . The spontaneous fission neutron spectra of 239Pu and, respectively, 240Pu, are approximated by Watt’s fission spectra, each spectrum using two evaluated parameters, denoted as and , respectively. The decay constant for actinide nuclide is denoted as , while denotes the fraction of decays that are spontaneous fission (the “spontaneous fission branching fraction”).
- The quantity denotes the atom density of isotope i in material m; , , where denotes the total number of isotopes, and denotes the total number of materials. The computation of uses the following well-known expression:
- The quantity represents the scattering transfer cross section from energy group into energy group . The transfer cross sections is computed in terms of the th-order Legendre coefficients (of the Legendre-expanded microscopic scattering cross section from energy group into energy group , for isotope ), which are tabulated parameters, using the following finite-order expansion:
- The total cross section for energy group and material , is computed for the PERP benchmark using the following expression:
- PARTISN [17] computes the quantity using the quantities , which are provided in data files for each isotope , and energy group , as follows:For the purposes of sensitivity analysis, the quantity , which denotes the number of neutrons that were produced per fission by isotope and energy group , can be obtained by using the relation , where the isotopic fission cross sections are available in data files for computing reaction rates.
- The quantity denotes the fission spectrum in energy group ; it is defined in PARTISN [17] as a space-independent quantity, as follows:
- The vector , which appears in the expression of the Boltzmann-operator , represents the “vector of imprecisely known model parameters”, comprising 21,976 components, which are presented in Table A3, below.
Symbol | Parameter Name | Number of Parameters |
---|---|---|
Multigroup microscopic total cross section for isotope and energy group | 180 | |
Multigroup microscopic scattering cross section for -th order Legendre expansion, from energy group into energy group , for isotope | 21,600 | |
Multigroup microscopic fission cross section and energy group | 60 | |
Average number of neutrons per fission for isotope and energy group | 60 | |
Fission spectrum for isotope and energy group | 60 | |
10 | ||
Isotopic number density for isotope and material | 6 | |
Total number of parameters: | 21,976 |
- (i)
- Thermal inelastic scattering, using the following expression for the respective differential cross section:
- (ii)
- Incoherent elastic scattering, using the following expression for the respective differential cross section: where is the Debye-Waller integral.
References
- Cacuci, D.G. Fourth-Order Predictive Modelling: II. 4th-BERRU-PM Methodology for Combining Measurements with Computations to Obtain Best-Estimate Results with Reduced Uncertainties. Am. J. Comp. Math. 2023, 13, 439–475. [Google Scholar] [CrossRef]
- Valentine, T.E. Polyethylene-Reflected Plutonium Metal Sphere Subcritical Noise Measurements, SUB-PU-METMIXED-001. In International Handbook of Evaluated Criticality Safety Benchmark Experiments; NEA/NSC/DOC(95)03/I-IX; Organization for Economic Co-Operation and Development: Paris, France; Nuclear Energy Agency: Paris, France, 2006. [Google Scholar]
- Jaynes, E.T. Information Theory and Statistical Mechanics. Phys. Rev. 1957, 106, 620. [Google Scholar] [CrossRef]
- Cacuci, D.G. Second-Order MaxEnt Predictive Modelling Methodology. I: Deterministically Incorporated Computational Model (2nd-BERRU-PMD). Am. J. Comp. Math. 2013, 13, 236–266, https://doi.org/10.4236/ajcm.2023.132013. See also: Cacuci, D.G. Second-Order MaxEnt Predictive Modelling Methodology. II: Probabilistically Incorporated Computational Model (2nd-BERRU-PMP). Am. J. Comp. Math. 2023, 13, 267–294. [Google Scholar] [CrossRef]
- SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, ORNL/TM 2005/39, Version 6; Oak Ridge National Laboratory: Oak Ridge, TN, USA, 2009.
- Venard, C.; Santamarina, A.; Leclainche, A.; Mournier, C. The R.I.B. Tool for the determination of computational bias and associated uncertainty in the CRISTAL criticality safety package. In Proceedings of the ANS Nuclear Criticality Safety Division Topical Meeting (NCSD 2009), Richland, WA, USA, 13–17 September 2009. [Google Scholar]
- Rabier, F. Overview of global data assimilation developments in numerical weather-prediction centers. Q. J. R. Meteorol. Soc. 2005, 131, 3215. [Google Scholar] [CrossRef]
- Lewis, J.M.; Lakshmivarahan, S.; Dhall, S.K. Dynamic Data Assimilation: A Least Square Approach; Cambridge University Press: Cambridge, UK, 2006. [Google Scholar]
- Lahoz, W.; Khattatov, B.; Ménard, R. (Eds.) Data Assimilation: Making Sense of Observations; Springer: Heidelberg, Germany, 2010. [Google Scholar]
- Práger, T.; Kelemen, F.D. Adjoint methods and their application in earth sciences. In Advanced Numerical Methods for Complex Environmental Models: Needs and Availability; Faragó, I., Havasi, Á., Zlatev, Z., Eds.; Bentham Science Publishers: Bussum, The Netherlands, 2013; Chapter 4, Part A; pp. 203–275. [Google Scholar]
- Cacuci, D.G.; Navon, M.I.; Ionescu-Bujor, M. Computational Methods for Data Evaluation and Assimilation; Chapman & Hall/CRC: Boca Raton, FL, USA, 2014. [Google Scholar]
- Cacuci, D.G. The nth-Order Comprehensive Adjoint Sensitivity Analysis Methodology: Overcoming the Curse of Dimensionality; Volume I: Linear Systems; Volume II: Application to a Large-Scale System; Volume III: Nonlinear Systems; Springer Nature: Cham, Switzerland, 2022. [Google Scholar]
- Bellman, R.E. Dynamic Programming; Rand Corporation, Princeton University Press: Princeton, NJ, USA, 1957; ISBN 978-0-691-07951-6. [Google Scholar]
- Cacuci, D.G.; Fang, R. Review of Fourth-Order Maximum Entropy Based Predictive Modelling and Illustrative Application to a Nuclear Reactor Benchmark: II. Best-Estimate Predicted Values and Uncertainties for Model Responses and Parameters. Energies 2024. accepted for publication. [Google Scholar]
- Tukey, J.W. The Propagation of Errors, Fluctuations and Tolerances; Technical Reports No. 10–12; Princeton University: Princeton, NJ, USA, 1957. [Google Scholar]
- Saltarelli, A.; Chan, K.; Scott, E.M. (Eds.) Sensitivity Analysis; John Wiley & Sons Ltd.: Chichester, UK, 2000. [Google Scholar]
- Alcouffe, R.E.; Baker, R.S.; Dahl, J.A.; Turner, S.A.; Ward, R. PARTISN: A Time-Dependent, Parallel Neutral Particle Transport Code System; LA-UR-08-07258; Los Alamos National Laboratory: Los Alamos, NM, USA, 2008.
- Conlin, J.L.; Parsons, D.K.; Gardiner, S.J.; Gray, M.; Lee, M.B.; White, M.C. MENDF71X: Multigroup Neutron Cross-Section Data Tables Based upon ENDF/B-VII.1X; Los Alamos National Laboratory Report LA-UR-15-29571; Los Alamos National Laboratory: Los Alamos, NM, USA, 2013.
- Chadwick, M.B.; Herman, M.; Obložinský, P.; Dunn, M.E.; Danon, Y.; Kahler, A.C.; Smith, D.L.; Pritychenko, B.; Arbanas, G.; Brewer, R.; et al. ENDF/B-VII.1: Nuclear data for science and technology: Cross sections, covariances, fission product yields and decay data. Nucl. Data Sheets 2011, 112, 2887–2996. [Google Scholar] [CrossRef]
- Wilson, W.B.; Perry, R.T.; Shores, E.F.; Charlton, W.S.; Parish, T.A.; Estes, G.P.; Brown, T.H.; Arthur, E.D.; Bozoian, M.; England, T.R.; et al. SOURCES4C: A code for calculating (α,n), spontaneous fission, and delayed neutron sources and spectra. In Proceedings of the American Nuclear Society/Radiation Protection and Shielding Division 12th Biennial Topical Meeting, Santa Fe, NM, USA, 14–18 April 2002. [Google Scholar]
- MacFarlane, R.; Muir, D.W.; Boicourt, R.M.; Kahler, A.C.; Conlin, J.L. The NJOY Nuclear Data Processing System, Version 2016; LA-UR-17-20093; Los Alamos National Lab. (LANL): Los Alamos, NM, USA, 2017.
g | 1st-Order | 2nd-Order | 3rd-Order | 4th-Order |
---|---|---|---|---|
1 | −8.471 × 10−6 | 7.636 × 10−7 | 6.322 × 10−8 | 1.460 × 10−7 |
2 | −2.060 × 10−5 | 2.280 × 10−6 | 4.516 × 10−8 | 4.956 × 10−7 |
3 | −6.810 × 10−5 | 9.021 × 10−6 | −4.677 × 10−7 | 2.245 × 10−6 |
4 | −3.932 × 10−4 | 6.673 × 10−5 | −8.758 × 10−6 | 2.039 × 10−5 |
5 | −2.449 × 10−3 | 5.549 × 10−4 | −1.216 × 10−4 | 2.142 × 10−4 |
6 | −9.342 × 10−3 | 2.935 × 10−3 | −1.123 × 10−3 | 1.553 × 10−3 |
7 | −7.589 × 10−2 | 3.949 × 10−2 | −2.690 × 10−2 | 3.513 × 10−2 |
8 | −9.115 × 10−2 | 5.604 × 10−2 | −4.380 × 10−2 | 5.536 × 10−2 |
9 | −1.358 × 10−1 | 1.014 × 10−1 | −9.758 × 10−2 | 1.416 × 10−1 |
10 | −1.659 × 10−1 | 1.428 × 10−1 | −1.604 × 10−1 | 2.582 × 10−1 |
11 | −1.899 × 10−1 | 1.849 × 10−1 | −2.385 × 10−1 | 4.233 × 10−1 |
12 | −4.446 × 10−1 | 6.620 × 10−1 | −1.373 × 100 | 3.815 × 100 |
13 | −5.266 × 10−1 | 9.782 × 10−1 | −2.590 × 100 | 9.015 × 100 |
14 | −5.772 × 10−1 | 1.262 × 100 | −3.991 × 100 | 1.650 × 101 |
15 | −5.820 × 10−1 | 1.391 × 100 | −4.581 × 100 | 2.208 × 101 |
16 | −1.164 × 100 | 4.460 × 100 | −2.530 × 101 | 1.890 × 102 |
17 | −1.173 × 100 | 4.853 × 100 | −2.991 × 101 | 2.432 × 102 |
18 | −1.141 × 100 | 4.828 × 100 | −3.049 × 101 | 2.543 × 102 |
19 | −1.094 × 100 | 4.619 × 100 | −2.913 × 101 | 2.428 × 102 |
20 | −1.033 × 100 | 4.284 × 100 | −2.655 × 101 | 2.175 × 102 |
21 | −9.692 × 10−1 | 3.937 × 100 | −2.388 × 101 | 1.915 × 102 |
22 | −8.917 × 10−1 | 3.515 × 100 | −2.069 × 101 | 1.609 × 102 |
23 | −8.262 × 10−1 | 3.177 × 100 | −1.823 × 101 | 1.382 × 102 |
24 | −7.495 × 10−1 | 2.792 × 100 | −1.552 × 101 | 1.140 × 102 |
25 | −7.087 × 10−1 | 2.604 × 100 | −1.427 × 101 | 1.033 × 102 |
26 | −6.529 × 10−1 | 2.349 × 100 | −1.260 × 101 | 8.932 × 101 |
27 | −5.845 × 10−1 | 2.039 × 100 | −1.061 × 101 | 7.288 × 101 |
28 | −5.474 × 10−1 | 1.885 × 100 | −9.678 × 100 | 6.565 × 101 |
29 | −5.439 × 10−1 | 1.891 × 100 | −9.800 × 100 | 6.705 × 101 |
30 | −9.366 × 100 | 4.296 × 102 | −2.966 × 104 | 2.720 × 106 |
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Cacuci, D.G.; Fang, R. Review of Fourth-Order Predictive Modeling and Illustrative Application to a Nuclear Reactor Benchmark. I. Typical High-Order Sensitivity and Uncertainty Analysis. Energies 2024, 17, 3874. https://doi.org/10.3390/en17163874
Cacuci DG, Fang R. Review of Fourth-Order Predictive Modeling and Illustrative Application to a Nuclear Reactor Benchmark. I. Typical High-Order Sensitivity and Uncertainty Analysis. Energies. 2024; 17(16):3874. https://doi.org/10.3390/en17163874
Chicago/Turabian StyleCacuci, Dan Gabriel, and Ruixian Fang. 2024. "Review of Fourth-Order Predictive Modeling and Illustrative Application to a Nuclear Reactor Benchmark. I. Typical High-Order Sensitivity and Uncertainty Analysis" Energies 17, no. 16: 3874. https://doi.org/10.3390/en17163874
APA StyleCacuci, D. G., & Fang, R. (2024). Review of Fourth-Order Predictive Modeling and Illustrative Application to a Nuclear Reactor Benchmark. I. Typical High-Order Sensitivity and Uncertainty Analysis. Energies, 17(16), 3874. https://doi.org/10.3390/en17163874