Comprehensive Second-Order Adjoint Sensitivity Analysis Methodology (2nd-ASAM) Applied to a Subcritical Experimental Reactor Physics Benchmark: I. Effects of Imprecisely Known Microscopic Total and Capture Cross Sections
Abstract
:1. Introduction
2. Methodology for Computing the Leakage Response of the Polyethylene-Reflected Plutonium Metal Sphere (PERP) Benchmark
- The quantity is the customary “group-flux” for group , and is the unknown state-function obtained by solving Equations (1) and (2).
- The vector denotes the outward unit normal vector at each point on the sphere’s outer boundary, denoted as .
- 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 spectrum of 239Pu and, respectively, 240Pu, is approximated by a Watts fission spectrum while using two evaluated parameters, denoted as and , respectively. The decay constant for actinide nuclide is denoted as , and 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 well-known expression
- The quantity represents the scattering transfer cross section from energy group into energy group and it is computed in terms of the -th order Legendre coefficient (of the Legendre-expanded microscopic scattering cross section from energy group into energy group for isotope ), which are tabulated parameters, in the following finite-order expansion:
- The total cross section for energy group and material , is computed for the PERP benchmark while using the following expression:
- To solve Equation (1), PARTISN [30] computes the quantity using directly the quantities , which are provided in data files for each isotope , and energy group , as followsFor the purposes of sensitivity analysis, the quantity , which quantifies 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 , and it is defined in PARTISN [30] 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” having 21,976 components, which are presented in Table 3. The mathematical expression of will be defined in the next section.
3. First-Order Sensitivities of the Total Leakage Response of the Polyethylene-Reflected Plutonium (PERP) Metal Sphere Benchmark with Respect to the Parameters Underlying the Benchmark’s Total Cross Sections
4. Second-Order Sensitivities of the PERP Total Leakage Response with Respect to the Parameters Underlying the Benchmark’s Total Cross Sections
4.1. Second-Order Unmixed Relative Sensitivities
- (1)
- As shown in Table 10, the 2nd-LASS-computed 1st-order relative sensitivity for the 30th group of isotope 1H has the value −9.366; the value of the corresponding absolute sensitivity computed using the central-difference method is −5.59657 × 105, which yields the relative sensitivity value ; the two values agree well with one another.
- (2)
- As shown in Table 10, the 2nd-LASS-computed unmixed 2nd-order relative sensitivity for the 30th group of isotope 1H has the value of 429.6; the value of the corresponding absolute sensitivity computed while using the central-difference method is 8.706316 × 105, which yields the relative sensitivity value ; the two values agree well with one another.
- (3)
- As shown in Table 9, the 2nd-LASS-computed unmixed 2nd-order relative sensitivity for the 30th group of isotope C has the value of 3.016; the value of the corresponding absolute sensitivity computed while using the central-difference method is 2.179357 × 105, which yields the relative sensitivity value ; the two values show good agreement with each other.
4.2. Second-Order Mixed Relative Sensitivities for the Leakge Response with respect to the Microscopic Total Cross Sections of Isotope 239Pu,
4.3. Second-Order Mixed Relative Sensitivities for the Leakge Response with Respect to the Microscopic Total Cross Sections of Isotope 239Pu and Isotope C,
4.4. Second-Order Mixed Relative Sensitivities for the Leakge Response with Respect to the Microscopic Total Cross Sections of Isotope 239Pu and Isotope 1H,
4.5. Second-Order Mixed Relative Sensitivities for the Leakge Response with Respect to the Microscopic Total Cross Sections of Isotope 240Pu and Isotope 1H,
4.6. Second-Order Mixed Relative Sensitivities for the Leakge Response with Respect to the Microscopic Total Cross Sections of Isotope C,
4.7. Second-Order Mixed Relative Sensitivities for the Leakge Response with Respect to the Microscopic Total Cross Sections of Isotope C and Isotope 1H,
4.8. Second-Order Mixed Relative Sensitivities for the Leakge Response with Respect to the Microscopic Total Cross Sections of Isotope 1H,
5. First- and Second-Order Sensitivities of the PERP Total Leakage Response with Respect to the Parameters Underlying the Benchmark’s Capture Cross Sections
5.1. First-Order Sensitivities
5.2. Second-Order Sensitivities
5.3. Numerical Results for
- (i)
- (ii)
- (iii)
- (iv)
- (v)
- (vi)
6. Second-Order Uncertainty Analysis of the PERP Leakage Response
- (i)
- Up to 2nd-order response sensitivities, the 1st-order moment (expected values) of a response has the following expression [12]:
- (ii)
- Up to 2nd-order response sensitivities, the 2nd-order moment (covariance) of two responses has the following expression [12]:
- (iii)
- Up to 2nd-order response sensitivities, the 3rd-order moment of three responses has the following expression [12]:
6.1. Uncorrelated Total Microscopic Cross Sections
6.2. Fully Correlated Total Microscopic Cross Sections
6.3. Numerical Results
6.3.1. Very Small (1%) Relative Standard Deviations
6.3.2. Typical (5%) Relative Standard Deviations
6.3.3. Large (10%) Relative Standard Deviations
7. Conclusions
- The 1st-order relative sensitivities with respect to the total cross sections for all the six isotopes are negative, as shown in Table 5, Table 6, Table 7, Table 8, Table 9 and Table 10, signifying that an increase in will cause a decrease in the leakage (i.e., fewer neutrons will leak out of the sphere). In contradistinction, all of the 2nd-order unmixed relative sensitivities are positive, which signifies that an increase in will cause an increase in .
- Comparing the results for the 1st-order relative sensitivities to those that were obtained for the 2nd-order unmixed relative sensitivities indicate that for isotope 1 (239Pu) and isotope 6 (1H), the absolute values of the 2nd-order sensitivities are generally greater than the corresponding values of the 1st-order sensitivities. On the other hand, for isotopes 2–5 (i.e., 240Pu, 69Ga, 71Ga, and C), the 1st-order and 2nd-order unmixed sensitivities are very small (generally of the order of 10−2 or less) and the absolute values of the 2nd-order unmixed relative sensitivities are all smaller than the corresponding values of the 1st-order relative sensitivities for all energy groups, except for the lowest-energy group of isotope C.
- For the isotopes 239Pu, 240Pu, 69Ga, and 71Ga, the largest 1st- and 2nd-order unmixed relative sensitivities occur for the 12th energy group of the total microscopic cross section, respectively. For the isotopes C and 1H, the largest relative sensitivities occur for the 30th, i.e., the lowest energy, group. Overall, the largest 1st- and 2nd-order unmixed relative sensitivities of all isotopes arise from the total microscopic cross section of isotopes 1H and 239Pu, and hence cause the most important subsequent effects that arise from the various mixed 2nd-order sensitivities.
- The 2nd-order mixed sensitivities , are generally positive. The corresponding relative sensitivities that involve the total cross sections of isotopes 2–5 (namely, 240Pu, 69Ga, 71Ga, and C) are generally small. However, some 2nd-order relative sensitivities involving the total cross sections of isotope 1 (239Pu) and isotope 6 (1H) are very large. Specially, among the total of second-order sensitivities, 720 elements have relative sensitivities that are greater than 1.0. The majority of these 720 elements stem from the submatrices , , and , characterized by energy groups . The parameters and are the most important among the entire total cross sections, since the largest sensitivities in the submatrices are always related to those two parameters. The overall largest relative sensitivity is , which occurs in group 30 for 1H, as noted in Table 10.
- The 1st-order relative sensitivities with respect to the capture cross sections for all the 6 isotopes are negative, as shown in Table 19, Table 20, Table 21, Table 22, Table 23 and Table 24, signifying that an increase in will cause a decrease in the leakage ; whereas, all of the unmixed 2nd-order relative sensitivities are positive. For all six isotopes, the values of both the 1st-order and the unmixed 2nd-order relative sensitivities with respect to the capture cross sections are very small; the values of the unmixed 2nd-order sensitivities are generally smaller than the corresponding values of the 1st-order sensitivities.
- The 1st-order and the unmixed 2nd-order absolute sensitivities of the leakage response with respect to the capture cross sections are identical to the corresponding 1st-order and unmixed 2nd-order absolute sensitivities for the total cross sections, respectively. However, the relative sensitivities for the capture cross sections are significantly smaller than those for the total cross sections; this is because the values for both the 1st- and unmixed 2nd-order relative sensitivities to the capture cross sections are scaled down from those of the corresponding total cross sections by factors of and , respectively.
- The mixed 2nd-order absolute sensitivities of the leakage response with respect to the capture cross sections, , are generally positive, and their values are identical to the corresponding absolute sensitivities to the total cross sections, . However, the values of the relative sensitivities for the capture cross-sections, are all smaller than 1.0, and they are smaller than the corresponding values of the relative sensitivities for the total cross sections, . The overall largest mixed 2nd-order relative sensitivity to the capture cross section is .
- Even when the group-averaged microscopic total cross sections are uncorrelated, the results in Table 25 indicate that the importance of the 2nd-order sensitivities relative to the importance of the 1st-order ones increase as the parameters uncertainties increase. The effects of the 2nd-order sensitivities are to increase the value of the expected response versus the computed response value, which shifts to positive values of the distribution of the leakage response in parameters space. Additionally, the contributions of the 2nd-order sensitivities to the response’s variance overtake the contributions of the 1st-order sensitivities to the response’s variance already for relatively small (ca. 5%) parameter standard deviations. These effects are rapidly amplified when the parameters are less precisely known. In particular, it has been shown that, for a uniform standard deviation of 10%, the 2nd-order sensitivities contribute 72% of the expected value for the leakage response by comparison to 28% contributed by the computed value . Furthermore, the contribution of the second-order sensitivities to the response variance is 847% larger than the contribution stemming from the first-order sensitivities. Thus, the customary procedure of neglecting second (and higher) order sensitivities and while considering that the computed value, , is the actual expected (i.e., mean) value, , of the distribution, would be in error by 362%. Hence, neglecting these second-order contributions would cause a very large non-conservative error by under-reporting of the response variance by a factor of 947%. In all cases, the second-order sensitivities cause the leakage distribution in parameter space to be skewed to positive values relative to the expected value, which, in turn, is significantly shifted to much larger positive values than the computed leakage . All in all, neglecting the second-order sensitivities would erroneously predict a Gaussian distribution for the leakage distribution in parameter space, centered about the computed leakage .
- As the results that are presented in Table 25 and Table 26 indicate that the mixed 2nd-order sensitivities play a very significant role in determining the moments of the leakage response distribution for correlated cross sections. The importance of the mixed 2nd-order sensitivities increases as the relative standard deviations for the cross sections increase. For example, for fully correlated cross sections, neglecting the 2nd-order sensitivities would cause an error as large as 2000% in the expected value of the leakage response, and up to 6000% in the variance of the leakage response. Furthermore, the effects of the mixed 2nd-order sensitivities underscore the need for reliable values for the correlations that might exist among the total cross sections, which are unavailable at this time.
Author Contributions
Acknowledgments
Conflicts of Interest
Nomenclature
Symbols | |
adjoint operator | |
atomic weight of isotope | |
, | parameters used in Watt’s fission spectra approximation for isotope |
forward operator | |
parameters in vector indexed by and | |
2nd-order moment (covariance) of two responses | |
boundary of energy group | |
expected value of the leakage response taking | |
fraction of isotope decays that are spontaneous fission events | |
parameters in vector indexed by and | |
total number of energy groups | |
number of isotopes | |
total number of parameters in vector | |
total number of parameters in vector | |
total number of parameters in vector | |
total number of parameters in vector | |
total number of parameters in vector | |
total number of parameters in vector | |
total number of parameters in vector | |
total number of parameters in vector | |
total number of parameters in vector | |
total number of parameters in vector | |
variable for the order of Legendre-expansion of the microscopic scattering cross sections, | |
total neutron leakage from the PERP sphere | |
total number of materials | |
Avogadro’s number | |
total number of fissionable isotopes | |
atom number density for isotope and material | |
Legendre and associated Legendre polynomials appreciate for the geometry | |
spherical harmonics appreciate for the geometry | |
source term in group | |
quadruple-correlations | |
, | responses |
spatial variable | |
external radius of the PoRP benchmark | |
outer surface of the PoRP sphere | |
standard deviation associated with the model parameter | |
parameters in vector indexed by and | |
triple-correlations | |
variance of the leakage response | |
weight fraction of isotope i in material m | |
Vectors and Matrices | |
vector of imprecisely known model parameters, | |
nominal values of the parameters in the vector | |
vector of imprecisely known total parameters, | |
vector of imprecisely known scatter parameters, | |
vector of imprecisely known fission parameters, | |
vector of imprecisely known total cross sections | |
vector of imprecisely known capture cross sections | |
vector of imprecisely known scattering cross sections | |
vector of imprecisely known fission cross sections | |
vector of imprecisely known parameters underlying the average number of neutrons per fission | |
of imprecisely known atom number densities | |
the outward unit normal vector at each point on the sphere’s outer boundary | |
vector of imprecisely known fission spectrum parameters | |
vector of imprecisely known source parameters | |
vector of first-order relative sensitivities of the leakage response | |
matrix of first-order relative sensitivities of the leakage response | |
Greek symbols | |
parameters in vector indexed by and | |
skewness | |
Kronecker-delta functionals | |
decay constant for isotope | |
third-order moment of the leakage response | |
number of neutrons produced per fission by isotope and energy group | |
the spontaneous emission of an average neutrons of an isotope | |
macroscopic quantity for fission for energy group in PARTISN | |
microscopic quantity for fission for energy group of isotope in PARTISN | |
correlation coefficient between parameters and | |
correlation coefficient between parameters and | |
correlation coefficient between parameters and | |
correlation coefficient between parameters and | |
mass density of material m, | |
cross sections | |
microscopic capture cross section in group of isotope | |
microscopic fission cross section in group of isotope | |
the order Legendre-expanded microscopic scattering cross section from energy group into energy group for isotope | |
microscopic total cross section in group of isotope | |
macroscopic total cross section for energy group | |
macroscopic fission cross section for energy group | |
macroscopic scattering transfer cross section from energy group into energy group | |
forward angular flux in group at point in direction | |
material fission spectrum in energy group | |
adjoint angular flux in group at point in direction | |
2nd-level adjoint functions in group at point in direction associated with the total cross section parameter indexed by (e.g., ) | |
directional variable | |
Subscripts, superscripts | |
first-order contributions from uncorrelated and normally-distributed parameters | |
first-order contributions from fully-correlated and normally-distributed parameters | |
2nd-order contributions from fully correlated parameters | |
2nd -order contributions from fully-correlated and normally-distributed parameters | |
2nd-order contributions from mixed sensitivities, correlated parameters | |
2nd-order contributions from uncorrelated parameters | |
2nd-order contributions from uncorrelated and normally-distributed parameters | |
fully-correlated parameters | |
fully-correlated and normally-distributed parameters | |
fission | |
energy group variable | |
, | energy group associated with parameter indexed by (e.g., , and ) or (e.g., , and ) |
index variable for isotopes, | |
, | isotope associated with the parameter indexed by (e.g., , and ) or (e.g., , and ) |
index variable for parameters | |
index variable for isotopes, | |
order of Legendre expansion associated with the microscopic scattering cross section | |
number of neutrons produced per fission | |
index variable for materials, | |
index variable for parameters | |
, | material associated with parameter indexed by (e.g., , and ) or (e.g., , and ) |
total | |
scatter | |
uncorrelated parameters | |
uncorrelated and normally-distributed parameters | |
Abbreviations | |
1st-Level adjoint sensitivity system | |
second-order adjoint sensitivity analysis methodology | |
Level adjoint sensitivity system | |
order of the finite expansion in Legendre polynomial | |
polyethylene-reflected plutonium |
References
- Wigner, E.P. Effect of small perturbations on pile period. Chicago Report CP-G-3048. 1945. [Google Scholar]
- Cacuci, D.G.; Weber, C.F.; Oblow, E.M.; Marable, J.H. Sensitivity theory for general systems of nonlinear equations. Nucl. Sci. Eng. 1980, 75, 88–110. [Google Scholar] [CrossRef]
- Cacuci, D.G. Sensitivity theory for nonlinear systems: I. Nonlinear functional analysis approach. J. Math. Phys. 1981, 22, 2794–2802. [Google Scholar] [CrossRef]
- Cacuci, D.G. Sensitivity theory for nonlinear systems: II. Extensions to additional classes of responses. J. Math. Phys. 1981, 22, 2803–2812. [Google Scholar] [CrossRef]
- Mitani, H. Higher-order perturbation method in reactor calculation. Nucl. Sci. Eng. 1973, 51, 180–188. [Google Scholar] [CrossRef]
- Seki, Y. Evaluation of the second-order perturbation terms by the generalized perturbation method. Nucl. Sci. Eng. 1973, 51, 243–251. [Google Scholar] [CrossRef]
- Gandini, A. Implicit and explicit higher-order perturbation methods for nuclear reactor analysis. Nucl. Sci. Eng. 1978, 67, 347–355. [Google Scholar] [CrossRef]
- Greenspan, E.; Gilai, D.; Oblow, E.M. Second-order generalized perturbation theory for source-driven systems. Nucl. Sci. Eng. 1978, 68, 1–9. [Google Scholar] [CrossRef]
- Cacuci, D.G.; Greenspan, E.; Marable, J.H.; Williams, M.L. Developments in sensitivity theory. In Proceedings of the ANS Topical Conference on 1980 Advances in Reactor Physics and Shielding, Sun Valley, ID, USA, 14–17 September 1980; pp. 692–704. [Google Scholar]
- Cacuci, D.G. Second-order adjoint sensitivity analysis methodology (2nd-ASAM) for computing exactly and efficiently first-and second-order sensitivities in large-scale linear systems: I. Computational methodology. J. Comput. Phys. 2015, 284, 687–699. [Google Scholar] [CrossRef]
- Cacuci, D.G. Second-order adjoint sensitivity analysis methodology (2nd-ASAM) for large-scale nonlinear systems: I. Theory. Nucl. Sci. Eng. 2016, 184, 16–30. [Google Scholar] [CrossRef]
- Cacuci, D.G. The Second-Order Adjoint Sensitivity Analysis Methodology; CRC Press: Boca Raton, FL, USA, 2018. [Google Scholar]
- Cacuci, D.G. Second-order adjoint sensitivity analysis methodology (2nd-ASAM) for computing exactly and efficiently first-and second-order sensitivities in large-scale linear systems: II. Illustrative application to a paradigm particle diffusion problem. J. Comput. Phys. 2015, 284, 700–717. [Google Scholar] [CrossRef]
- Cacuci, D.G. Second-order adjoint sensitivity and uncertainty analysis of a benchmark heat transport problem: I. Analytical results. Nucl. Sci. Eng. 2016, 183, 1–21. [Google Scholar] [CrossRef]
- Cacuci, D.G.; Ilic, M.; Badea, M.C.; Fang, R. Second-order adjoint sensitivity and uncertainty analysis of a benchmark heat transport problem, II: Computational results using G4M reactor thermal-hydraulics parameters. Nucl. Sci. Eng. 2016, 183, 22–38. [Google Scholar] [CrossRef]
- Cacuci, D.G. Second-order adjoint sensitivity analysis methodology (2nd-ASAM) for large-scale nonlinear systems: II. Illustrative application to a paradigm nonlinear heat conduction benchmark. Nucl. Sci. Eng. 2016, 184, 31–52. [Google Scholar] [CrossRef]
- Cacuci, D.G.; Favorite, J.A. Second-order sensitivity analysis of uncollided particle contributions to radiation detector responses. Nucl. Sci. Eng. 2018, 190, 105–133. [Google Scholar] [CrossRef]
- Nuclear Energy Agency. International Handbook of Evaluated Criticality Safety Benchmark Experiments; OECD Nuclear Energy Agency: Paris, France, 2016. [Google Scholar]
- Brandon, E. Assembly of 239Pu Ball for Criticality Experiment; CMB-11-FAB-80-65; Los Alamos National Laboratory: Los Alamos, NM, USA, 1980.
- Hutchinson, J.; Nelson, M.; Grove, T.; Arthur, J.; McKenzie, G.; Bahran, R.; Cutler, T. Validation of statistical uncertainties in subcritical benchmark measurements: Part I—Theory and simulations. Ann. Nucl. Energy 2018, 125, 50–62. [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; Nuclear Energy Agency: Paris, France, 2006. [Google Scholar]
- Mattingly, J.K. Polyethylene-Reflected Plutonium Metal Sphere: Subcritical Neutron and Gamma Measurements; SAND2009-5804 Rev. 3; Sandia National Laboratories: Albuquerque, NM, USA, 2012.
- Miller, E.C.; Mattingly, J.K.; Clarke, S.D.; Solomon, C.J.; Dennis, B.; Meldrum, A.; Pozzi, S.A. Computational evaluation of neutron multiplicity measurements of polyethylene-reflected plutonium metal. Nucl. Sci. Eng. 2014, 176, 167–185. [Google Scholar] [CrossRef]
- Cacuci, D.G. Application of the second-order comprehensive adjoint sensitivity analysis methodology to compute 1st-and 2nd-order sensitivities of flux functionals in a multiplying system with source. Nucl. Sci. Eng. 2019, 193, 555–600. [Google Scholar] [CrossRef]
- Cacuci, D.G. Second-order sensitivities of a general functional of the forward and adjoint flues in a multiplying nuclear system with source. Nucl. Eng. Des. 2019, 344, 83–106. [Google Scholar] [CrossRef]
- Cacuci, D.G. Second-order adjoint sensitivity analysis of a general ratio of functionals of the forward and adjoint fluxes in a multiplying nuclear system with source. Ann. Nucl. Energy 2020, 135, 106956. [Google Scholar] [CrossRef]
- Gandini, A. A generalized perturbation method for bilinear functionals of the real and adjoint neutron fluxes. J. Nucl. Energy 1967, 21, 755–765. [Google Scholar] [CrossRef]
- Stacey, W.M. Variational estimates and generalized perturbation theory for ratios of linear and bilinear functionals. J. Math. Phys. 1972, 13, 1119–1125. [Google Scholar] [CrossRef]
- Stacey, W.M., Jr. Variational Methods in Nuclear Reactor Physics; Academic Press: New York, NY, USA, 1974. [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.
- 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]
- 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. [CrossRef]
- 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]
- Prinja, A.K.; Larsen, E.W. General principles of neutron transport. In Handbook of Nuclear Engineering; Cacuci, D.G., Ed.; Springer: Berlin, Germany, 2010; Chapter 5; Volume 1, pp. 427–542. [Google Scholar]
- Solomon, C.J. MCNP Intrinsic Source Constructor (MISC): A User’s Guide; Los Alamos National Laboratory Internal Memorandum LA–UR–12–20252; Los Alamos National Laboratory: Los Alamos, NM, USA, 2012.
- Cacuci, D.G. BERRU Predictive Modeling: Best Estimate Results with Reduced Uncertainties; Springer: Heidelberg, Germany; New York, NY, USA, 2018. [Google Scholar]
- Fang, R.; Cacuci, D.G. Comprehensive second-order adjoint sensitivity analysis methodology (2nd-ASAM) applied to a subcritical experimental reactor physics benchmark: II. Effects of imprecisely known microscopic scattering cross sections. Energies 2019, 12, 4114. [Google Scholar] [CrossRef]
- Cacuci, D.G.; Fang, R.; Favorite, J.A.; Badea, M.C.; di Rocco, F. Comprehensive second-order adjoint sensitivity analysis methodology (2nd-ASAM) applied to a subcritical experimental reactor physics benchmark: III. Effects of imprecisely known microscopic fission cross sections and average number of neutrons per fission. Energies 2019, 12, 4100. [Google Scholar] [CrossRef]
- Fang, R.; Cacuci, D.G. Comprehensive second-order adjoint sensitivity analysis methodology (2nd-ASAM) applied to a subcritical experimental reactor physics benchmark: IV. Effects of imprecisely known source parameters. Energies. submitted.
- Cacuci, D.G.; Fang, R.; Favorite, J.A. Comprehensive second-order adjoint sensitivity analysis methodology (2nd-ASAM) applied to a subcritical experimental reactor physics benchmark: V. Effects of imprecisely known isotopic number densities, fission spectrum and overall conclusions. Energies. submitted.
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 (C) | 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 |
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 | |
Source parameters: | 10 | |
Isotopic number density for isotope and material | 6 | |
Total number of parameters: | 21,976 | |
Symbol | Parameter name | Number of parameters |
Multigroup microscopic capture cross section for isotope and energy group | 180 |
(239Pu) | (240Pu) | (69Ga) | (71Ga) | (C) | (1H) | |
---|---|---|---|---|---|---|
(239Pu) | 98 elements with absolute values >1.0 | Max. value = at g = 12, g′ = 12 | Max. value = at g = 12, g′ = 12 | Max. value = at g = 12, g′ = 12 | 10 elements with absolute values >1.0 | 135 elements with absolute values >1.0 |
(240Pu) | Max. value = at g = 27, g′ = 27 | Max. value = at g = 12, g′ = 12 | Max. value = at g = 12, g′ = 12 | Max. value = at g = 12, g′ = 12 | 3 elements with absolute values >1.0 | |
(69Ga) | Max. value = at g = 13, g′ = 13 | Max. value = at g = 13, g′ = 13 | Max. value = at g = 12, g′ = 16 | Max. value = at g = 12, g′ = 30 | ||
(71Ga) | Max. value = at g = 12, g′ = 12 | Max. value = at g = 12, g′ = 30 | Max. value = at g = 12, g′ = 30 | |||
(C) | 1 element with absolute value >1.0 | 33 elements with absolute values >1.0 | ||||
(1H) | 259 elements with absolute values >1.0 |
g | 1st-Order | 2nd-Order | g | 1st-Order | 2nd-Order |
---|---|---|---|---|---|
1 | −0.0003 | 0.0003 | 16 | −0.779 | 3.487 |
2 | −0.0007 | 0.0005 | 17 | −0.364 | 1.578 |
3 | −0.0019 | 0.0015 | 18 | −0.227 | 0.995 |
4 | −0.009 | 0.007 | 19 | −0.181 | 0.789 |
5 | −0.046 | 0.043 | 20 | −0.155 | 0.601 |
6 | −0.135 | 0.162 | 21 | −0.137 | 0.479 |
7 | −0.790 | 1.987 | 22 | −0.099 | 0.297 |
8 | −0.726 | 1.768 | 23 | −0.081 | 0.205 |
9 | −0.843 | 2.205 | 24 | −0.051 | 0.123 |
10 | −0.845 | 2.177 | 25 | −0.060 | 0.138 |
11 | −0.775 | 1.879 | 26 | −0.063 | 0.158 |
12 | −1.320 | 4.586 | 27 | −0.017 | 0.022 |
13 | −1.154 | 4.039 | 28 | −0.003 | 0.002 |
14 | −0.952 | 3.435 | 29 | −0.035 | 0.072 |
15 | −0.690 | 2.487 | 30 | −0.461 | 1.353 |
g | 1st-Order | 2nd-Order | g | 1st-Order | 2nd-Order |
---|---|---|---|---|---|
1 | −2.060 × 10−5 | 1.052 × 10−6 | 16 | −4.864 × 10−2 | 1.357 × 10−2 |
2 | −4.117 × 10−5 | 2.089 × 10−6 | 17 | −2.236 × 10−2 | 5.943 × 10−3 |
3 | −1.192 × 10−4 | 6.055 × 10−6 | 18 | −1.358 × 10−2 | 3.571 × 10−3 |
4 | −5.638 × 10−4 | 2.947 × 10−5 | 19 | −1.021 × 10−2 | 2.522 × 10−3 |
5 | −2.894 × 10−3 | 1.730 × 10−4 | 20 | −8.914 × 10−3 | 2.000 × 10−3 |
6 | −8.513 × 10−3 | 6.485 × 10−4 | 21 | −6.716 × 10−3 | 1.159 × 10−3 |
7 | −4.958 × 10−2 | 7.836 × 10−3 | 22 | −4.676 × 10−3 | 6.577 × 10−4 |
8 | −4.574 × 10−2 | 7.026 × 10−3 | 23 | −7.458 × 10−3 | 1.760 × 10−3 |
9 | −5.318 × 10−2 | 8.769 × 10−3 | 24 | −4.371 × 10−3 | 8.923 × 10−4 |
10 | −5.345 × 10−2 | 8.711 × 10−3 | 25 | −8.131 × 10−4 | 2.522 × 10−5 |
11 | −4.909 × 10−2 | 7.547 × 10−3 | 26 | −9.171 × 10−4 | 3.322 × 10−5 |
12 | −8.364 × 10−2 | 1.842 × 10−2 | 27 | −1.862 × 10−2 | 2.499 × 10−2 |
13 | −7.145 × 10−2 | 1.548 × 10−2 | 28 | −9.671 × 10−3 | 1.545 × 10−2 |
14 | −5.953 × 10−2 | 1.342 × 10−2 | 29 | −1.364 × 10−4 | 1.120 × 10−6 |
15 | −4.267 × 10−2 | 9.506 × 10−3 | 30 | −7.909 × 10−3 | 3.978 × 10−4 |
g | 1st-Order | 2nd-Order | g | 1st-Order | 2nd-Order |
---|---|---|---|---|---|
1 | −9.214 × 10−7 | 2.104 × 10−9 | 16 | −2.551 × 10−3 | 3.733 × 10−5 |
2 | −1.974 × 10−6 | 4.804 × 10−9 | 17 | −1.262 × 10−3 | 1.893 × 10−5 |
3 | −6.012 × 10−6 | 1.541 × 10−8 | 18 | −8.411 × 10−4 | 1.371 × 10−5 |
4 | −3.036 × 10−5 | 8.545 × 10−8 | 19 | −8.605 × 10−4 | 1.790 × 10−5 |
5 | −1.587 × 10−4 | 5.204 × 10−7 | 20 | −6.458 × 10−4 | 1.050 × 10−5 |
6 | −4.353 × 10−4 | 1.696 × 10−6 | 21 | −3.919 × 10−4 | 3.949 × 10−6 |
7 | −2.107 × 10−3 | 1.415 × 10−5 | 22 | −1.489 × 10−4 | 6.668 × 10−7 |
8 | −1.717 × 10−3 | 9.897 × 10−6 | 23 | −1.104 × 10−4 | 3.859 × 10−7 |
9 | −1.912 × 10−3 | 1.133 × 10−5 | 24 | −3.199 × 10−5 | 4.778 × 10−8 |
10 | −1.956 × 10−3 | 1.166 × 10−5 | 25 | −1.726 × 10−5 | 1.136 × 10−8 |
11 | −1.943 × 10−3 | 1.182 × 10−5 | 26 | −5.147 × 10−5 | 1.046 × 10−7 |
12 | −3.756 × 10−3 | 3.714 × 10−5 | 27 | −2.586 × 10−5 | 4.825 × 10−8 |
13 | −3.522 × 10−3 | 3.762 × 10−5 | 28 | −8.496 × 10−7 | 1.192 × 10−10 |
14 | −2.987 × 10−3 | 3.371 × 10−5 | 29 | −6.754 × 10−7 | 2.747 × 10−11 |
15 | −2.182 × 10−3 | 2.485 × 10−5 | 30 | −2.542 × 10−5 | 4.111 × 10−9 |
g | 1st-Order | 2nd-Order | g | 1st-Order | 2nd-Order |
---|---|---|---|---|---|
1 | −6.266 × 10−7 | 9.730 × 10−10 | 16 | −1.662 × 10−3 | 1.585 × 10−5 |
2 | −1.345 × 10−6 | 2.230 × 10−9 | 17 | −8.176 × 10−4 | 7.950 × 10−6 |
3 | −4.103 × 10−6 | 7.176 × 10−9 | 18 | −5.318 × 10−4 | 5.479 × 10−6 |
4 | −2.069 × 10−5 | 3.967 × 10−8 | 19 | −4.939 × 10−4 | 5.898 × 10−6 |
5 | −1.072 × 10−4 | 2.374 × 10−7 | 20 | −3.976 × 10−4 | 3.979 × 10−6 |
6 | −2.906 × 10−4 | 7.557 × 10−7 | 21 | −2.344 × 10−4 | 1.413 × 10−6 |
7 | −1.397 × 10−3 | 6.218 × 10−6 | 22 | −2.170 × 10−3 | 1.416 × 10−4 |
8 | −1.149 × 10−3 | 4.436 × 10−6 | 23 | −1.337 × 10−4 | 5.659 × 10−7 |
9 | −1.295 × 10−3 | 5.202 × 10−6 | 24 | −1.322 × 10−5 | 8.156 × 10−9 |
10 | −1.327 × 10−3 | 5.368 × 10−6 | 25 | −7.518 × 10−6 | 2.154 × 10−9 |
11 | −1.318 × 10−3 | 5.439 × 10−6 | 26 | −2.313 × 10−5 | 2.112 × 10−8 |
12 | −2.549 × 10−3 | 1.710 × 10−5 | 27 | −1.201 × 10−5 | 1.041 × 10−8 |
13 | −2.375 × 10−3 | 1.711 × 10−5 | 28 | −4.131 × 10−7 | 2.818 × 10−11 |
14 | −2.005 × 10−3 | 1.521 × 10−5 | 29 | −3.512 × 10−7 | 7.429 × 10−12 |
15 | −1.481 × 10−3 | 1.145 × 10−5 | 30 | −1.665 × 10−5 | 1.764 × 10−9 |
g | 1st-Order | 2nd-Order | g | 1st-Order | 2nd-Order |
---|---|---|---|---|---|
1 | −9.992 × 10−6 | 1.066 × 10−6 | 16 | −2.074 × 10−1 | 1.415 × 10−1 |
2 | −2.017 × 10−5 | 2.185 × 10−6 | 17 | −1.665 × 10−1 | 9.779 × 10−2 |
3 | −6.373 × 10−5 | 7.901 × 10−6 | 18 | −1.439 × 10−1 | 7.678 × 10−2 |
4 | −2.996 × 10−4 | 3.873 × 10−5 | 19 | −1.310 × 10−1 | 6.625 × 10−2 |
5 | −1.597 × 10−3 | 2.359 × 10−4 | 20 | −1.212 × 10−1 | 5.905 × 10−2 |
6 | −4.403 × 10−3 | 6.521 × 10−4 | 21 | −1.129 × 10−1 | 5.347 × 10−2 |
7 | −3.698 × 10−2 | 9.376 × 10−3 | 22 | −1.036 × 10−1 | 4.747 × 10−2 |
8 | −4.631 × 10−2 | 1.447 × 10−2 | 23 | −9.589 × 10−2 | 4.280 × 10−2 |
9 | −4.502 × 10−2 | 1.114 × 10−2 | 24 | −8.693 × 10−2 | 3.756 × 10−2 |
10 | −5.135 × 10−2 | 1.368 × 10−2 | 25 | −8.213 × 10−2 | 3.496 × 10−2 |
11 | −5.645 × 10−2 | 1.633 × 10−2 | 26 | −7.550 × 10−2 | 3.142 × 10−2 |
12 | −1.345 × 10−1 | 6.055 × 10−2 | 27 | −6.727 × 10−2 | 2.701 × 10−2 |
13 | −1.529 × 10−1 | 8.249 × 10−2 | 28 | −6.224 × 10−2 | 2.437 × 10−2 |
14 | −1.504 × 10−1 | 8.573 × 10−2 | 29 | −5.995 × 10−2 | 2.298 × 10−2 |
15 | −1.299 × 10−1 | 6.928 × 10−2 | 30 | −7.847 × 10−1 | 3.016 |
g | 1st-Order | 2nd-Order | g | 1st-Order | 2nd-Order |
---|---|---|---|---|---|
1 | −8.471 × 10−6 | 7.636 × 10−7 | 16 | −1.164 | 4.460 |
2 | −2.060 × 10−5 | 2.280 × 10−6 | 17 | −1.173 | 4.853 |
3 | −6.810 × 10−5 | 9.021 × 10−6 | 18 | −1.141 | 4.828 |
4 | −3.932 × 10−4 | 6.673 × 10−5 | 19 | −1.094 | 4.619 |
5 | −2.449 × 10−3 | 5.549 × 10−4 | 20 | −1.033 | 4.284 |
6 | −9.342 × 10−3 | 2.935 × 10−3 | 21 | −9.692 | 3.937 |
7 | −7.589 × 10−2 | 3.949 × 10−2 | 22 | −8.917 × 10−1 | 3.515 |
8 | −9.115 × 10−2 | 5.604 × 10−2 | 23 | −8.262 × 10−1 | 3.177 |
9 | −1.358 × 10−1 | 1.014 × 10−1 | 24 | −7.495 × 10−1 | 2.792 |
10 | −1.659 × 10−1 | 1.428 × 10−1 | 25 | −7.087 × 10−1 | 2.604 |
11 | −1.899 × 10−1 | 1.849 × 10−1 | 26 | −6.529 × 10−1 | 2.349 |
12 | −4.446 × 10−1 | 6.620 × 10−1 | 27 | −5.845 × 10−1 | 2.039 |
13 | −5.266 × 10−1 | 9.782 × 10−1 | 28 | −5.474 × 10−1 | 1.885 |
14 | −5.772 × 10−1 | 1.262 | 29 | −5.439 × 10−1 | 1.891 |
15 | −5.820 × 10−1 | 1.391 | 30 | −9.366 | 4.296 × 102 |
g′ = 6 | 7 | 8 | 9 | 10 | 11 | 12 | 13 | 14 | 15 | 16 | 17 | |
---|---|---|---|---|---|---|---|---|---|---|---|---|
g = 6 | 0.162 | 0.194 | 0.176 | 0.204 | 0.205 | 0.188 | 0.319 | 0.280 | 0.233 | 0.170 | 0.194 | 0.091 |
7 | 0.194 | 1.987 | 1.022 | 1.182 | 1.179 | 1.080 | 1.842 | 1.622 | 1.349 | 0.985 | 1.123 | 0.530 |
8 | 0.176 | 1.022 | 1.768 | 1.107 | 1.092 | 0.994 | 1.695 | 1.493 | 1.244 | 0.909 | 1.037 | 0.490 |
9 | 0.204 | 1.182 | 1.107 | 2.205 | 1.279 | 1.157 | 1.970 | 1.735 | 1.445 | 1.056 | 1.205 | 0.570 |
10 | 0.205 | 1.179 | 1.092 | 1.279 | 2.178 | 1.175 | 1.975 | 1.740 | 1.448 | 1.059 | 1.209 | 0.573 |
11 | 0.188 | 1.080 | 0.994 | 1.157 | 1.175 | 1.879 | 1.825 | 1.591 | 1.328 | 0.971 | 1.109 | 0.527 |
12 | 0.319 | 1.842 | 1.695 | 1.970 | 1.975 | 1.825 | 4.586 | 2.733 | 2.264 | 1.655 | 1.897 | 0.906 |
13 | 0.280 | 1.622 | 1.493 | 1.735 | 1.740 | 1.591 | 2.733 | 4.039 | 2.013 | 1.462 | 1.676 | 0.804 |
14 | 0.233 | 1.349 | 1.244 | 1.445 | 1.448 | 1.328 | 2.264 | 2.013 | 3.435 | 1.249 | 1.390 | 0.672 |
15 | 0.170 | 0.985 | 0.909 | 1.056 | 1.059 | 0.971 | 1.655 | 1.462 | 1.249 | 2.487 | 1.076 | 0.493 |
16 | 0.194 | 1.123 | 1.037 | 1.205 | 1.209 | 1.109 | 1.897 | 1.676 | 1.390 | 1.076 | 3.487 | 0.608 |
17 | 0.091 | 0.530 | 0.490 | 0.570 | 0.573 | 0.527 | 0.906 | 0.804 | 0.672 | 0.493 | 0.608 | 1.578 |
Energy Groups | g = 7 g′ = 30 | g = 9 g′ = 30 | g = 10 g′ = 30 | g = 11 g′ = 30 | g = 12 g′ = 30 | g = 13 g′ = 30 | g = 14 g′ = 30 | g = 15 g′ = 30 | g = 16 g′ = 30 | g = 30 g′ = 30 |
---|---|---|---|---|---|---|---|---|---|---|
Values | 1.019 | 1.105 | 1.115 | 1.032 | 1.789 | 1.607 | 1.360 | 1.006 | 1.159 | 1.260 |
g′ = 13 | 14 | 15 | 16 | 17 | 18 | 19 | 20 | 21 | |
---|---|---|---|---|---|---|---|---|---|
g = 6 | 0.100 | 0.115 | 0.120 | 0.246 | 0.253 | 0.248 | 0.239 | 0.227 | 0.213 |
7 | 0.585 | 0.671 | 0.699 | 1.437 | 1.476 | 1.449 | 1.396 | 1.323 | 1.243 |
8 | 0.544 | 0.624 | 0.649 | 1.335 | 1.370 | 1.346 | 1.296 | 1.228 | 1.154 |
9 | 0.636 | 0.729 | 0.759 | 1.561 | 1.602 | 1.573 | 1.515 | 1.435 | 1.348 |
10 | 0.643 | 0.737 | 0.766 | 1.576 | 1.617 | 1.588 | 1.529 | 1.448 | 1.361 |
11 | 0.596 | 0.682 | 0.709 | 1.459 | 1.497 | 1.469 | 1.415 | 1.340 | 1.260 |
12 | 1.049 | 1.182 | 1.228 | 2.529 | 2.596 | 2.548 | 2.454 | 2.324 | 2.184 |
13 | 1.132 | 1.076 | 1.103 | 2.271 | 2.332 | 2.290 | 2.205 | 2.088 | 1.963 |
14 | 0.718 | 1.117 | 0.946 | 1.919 | 1.972 | 1.937 | 1.866 | 1.768 | 1.661 |
15 | 0.527 | 0.611 | 0.878 | 1.428 | 1.458 | 1.433 | 1.381 | 1.309 | 1.230 |
16 | 0.617 | 0.712 | 0.749 | 1.927 | 1.677 | 1.646 | 1.588 | 1.505 | 1.415 |
17 | 0.310 | 0.360 | 0.379 | 0.794 | 1.055 | 0.785 | 0.757 | 0.718 | 0.676 |
18 | 0.205 | 0.240 | 0.255 | 0.535 | 0.565 | 0.731 | 0.475 | 0.451 | 0.424 |
19 | 0.169 | 0.198 | 0.211 | 0.444 | 0.469 | 0.472 | 0.600 | 0.356 | 0.335 |
20 | 0.147 | 0.172 | 0.183 | 0.387 | 0.408 | 0.410 | 0.402 | 0.497 | 0.279 |
21 | 0.131 | 0.154 | 0.164 | 0.346 | 0.365 | 0.366 | 0.359 | 0.347 | 0.421 |
22 | 0.096 | 0.113 | 0.121 | 0.254 | 0.267 | 0.268 | 0.263 | 0.253 | 0.245 |
23 | 0.079 | 0.093 | 0.098 | 0.207 | 0.218 | 0.218 | 0.214 | 0.206 | 0.198 |
24 | 0.050 | 0.059 | 0.063 | 0.133 | 0.139 | 0.140 | 0.137 | 0.132 | 0.126 |
25 | 0.060 | 0.070 | 0.075 | 0.157 | 0.164 | 0.164 | 0.161 | 0.155 | 0.148 |
26 | 0.063 | 0.074 | 0.078 | 0.164 | 0.173 | 0.172 | 0.169 | 0.162 | 0.156 |
27 | 0.017 | 0.020 | 0.021 | 0.045 | 0.047 | 0.047 | 0.046 | 0.044 | 0.042 |
28 | 0.003 | 0.004 | 0.004 | 0.009 | 0.009 | 0.009 | 0.009 | 0.009 | 0.009 |
29 | 0.035 | 0.041 | 0.044 | 0.091 | 0.096 | 0.096 | 0.093 | 0.090 | 0.086 |
30 | 0.469 | 0.550 | 0.585 | 1.226 | 1.283 | 1.280 | 1.252 | 1.204 | 1.153 |
g′ = 22 | 23 | 24 | 25 | 26 | 27 | 28 | 29 | 30 | |
g = 6 | 0.196 | 0.181 | 0.164 | 0.156 | 0.144 | 0.128 | 0.120 | 0.121 | 2.086 |
7 | 1.142 | 1.058 | 0.957 | 0.909 | 0.838 | 0.746 | 0.700 | 0.704 | 12.17 |
8 | 1.060 | 0.982 | 0.888 | 0.843 | 0.777 | 0.693 | 0.650 | 0.653 | 11.29 |
9 | 1.239 | 1.148 | 1.038 | 0.986 | 0.908 | 0.810 | 0.759 | 0.763 | 13.19 |
10 | 1.251 | 1.159 | 1.048 | 0.995 | 0.917 | 0.817 | 0.766 | 0.770 | 13.31 |
11 | 1.157 | 1.072 | 0.970 | 0.921 | 0.848 | 0.756 | 0.709 | 0.713 | 12.32 |
12 | 2.007 | 1.859 | 1.682 | 1.596 | 1.471 | 1.312 | 1.230 | 1.235 | 21.35 |
13 | 1.804 | 1.671 | 1.512 | 1.435 | 1.322 | 1.179 | 1.105 | 1.110 | 19.18 |
14 | 1.527 | 1.414 | 1.280 | 1.214 | 1.119 | 0.998 | 0.935 | 0.939 | 16.23 |
15 | 1.130 | 1.047 | 0.947 | 0.899 | 0.828 | 0.739 | 0.693 | 0.695 | 12.01 |
16 | 1.301 | 1.205 | 1.091 | 1.035 | 0.954 | 0.850 | 0.798 | 0.801 | 13.83 |
17 | 0.622 | 0.576 | 0.521 | 0.495 | 0.456 | 0.407 | 0.382 | 0.384 | 6.622 |
18 | 0.391 | 0.362 | 0.328 | 0.312 | 0.287 | 0.256 | 0.240 | 0.242 | 4.170 |
19 | 0.309 | 0.287 | 0.259 | 0.246 | 0.227 | 0.202 | 0.190 | 0.191 | 3.297 |
20 | 0.257 | 0.239 | 0.216 | 0.205 | 0.189 | 0.169 | 0.158 | 0.159 | 2.748 |
21 | 0.222 | 0.206 | 0.186 | 0.177 | 0.163 | 0.146 | 0.137 | 0.137 | 2.372 |
22 | 0.293 | 0.148 | 0.134 | 0.127 | 0.117 | 0.105 | 0.098 | 0.099 | 1.706 |
23 | 0.188 | 0.228 | 0.107 | 0.102 | 0.094 | 0.084 | 0.079 | 0.079 | 1.366 |
24 | 0.120 | 0.115 | 0.140 | 0.065 | 0.060 | 0.054 | 0.050 | 0.051 | 0.873 |
25 | 0.140 | 0.134 | 0.127 | 0.159 | 0.070 | 0.062 | 0.058 | 0.059 | 1.012 |
26 | 0.147 | 0.140 | 0.132 | 0.130 | 0.163 | 0.066 | 0.062 | 0.062 | 1.069 |
27 | 0.040 | 0.038 | 0.036 | 0.035 | 0.034 | 0.043 | 0.017 | 0.017 | 0.296 |
28 | 0.008 | 0.008 | 0.007 | 0.007 | 0.007 | 0.006 | 0.008 | 0.003 | 0.058 |
29 | 0.081 | 0.077 | 0.072 | 0.070 | 0.067 | 0.064 | 0.063 | 0.084 | 0.581 |
30 | 1.087 | 1.033 | 0.969 | 0.938 | 0.894 | 0.837 | 0.812 | 0.818 | 15.04 |
Energy Groups | g = 12 g′ = 30 | g = 13 g′ = 30 | g = 14 g′ = 30 | g = 15 g′ = 30 | g = 16 g′ = 30 | g = 17 g′ = 30 | g = 18 g′ = 30 | g = 19 g′ = 30 | g = 20 g′ = 30 | g = 21 g′ = 30 | g = 22 g′ = 30 |
---|---|---|---|---|---|---|---|---|---|---|---|
Values | 1.945 | 2.446 | 2.598 | 2.380 | 4.003 | 3.353 | 2.979 | 2.772 | 2.618 | 2.494 | 2.352 |
Energy Groups | g = 23 g′ = 30 | g = 24 g′ = 30 | g = 25 g′ = 30 | g = 26 g′ = 30 | g = 27 g′ = 30 | g = 28 g′ = 30 | g = 29 g′ = 30 | g = 30 g′ = 16 | g = 30 g′ = 17 | g = 30 g′ = 18 | g = 30 g′ = 19 |
Values | 2.238 | 2.103 | 2.037 | 1.942 | 1.814 | 1.740 | 1.696 | 1.883 | 1.979 | 1.979 | 1.939 |
Energy Groups | g = 30 g′ = 20 | g = 30 g′ = 21 | g = 30 g′ = 22 | g = 30 g′ = 23 | g = 30 g′ = 24 | g = 30 g′ = 25 | g = 30 g′ = 26 | g = 30 g′ = 27 | g = 30 g′ = 28 | g = 30 g′ = 29 | g = 30 g′ = 30 |
Values | 1.868 | 1.793 | 1.696 | 1.615 | 1.519 | 1.473 | 1.407 | 1.321 | 1.282 | 1.289 | 36.00 |
g′ = 12 | 13 | 14 | 15 | 16 | 17 | 18 | 19 | 20 | 21 | 22 | |
---|---|---|---|---|---|---|---|---|---|---|---|
g = 12 | 0.653 | 0.315 | 0.340 | 0.356 | 0.740 | 0.763 | 0.751 | 0.725 | 0.688 | 0.648 | 0.597 |
13 | 0.315 | 0.974 | 0.471 | 0.471 | 0.976 | 1.005 | 0.988 | 0.953 | 0.904 | 0.851 | 0.784 |
14 | 0.340 | 0.471 | 1.261 | 0.579 | 1.158 | 1.192 | 1.172 | 1.130 | 1.072 | 1.009 | 0.930 |
15 | 0.356 | 0.471 | 0.579 | 1.391 | 1.255 | 1.277 | 1.255 | 1.210 | 1.148 | 1.081 | 0.996 |
16 | 0.740 | 0.976 | 1.158 | 1.255 | 4.461 | 2.700 | 2.647 | 2.553 | 2.421 | 2.280 | 2.100 |
17 | 0.763 | 1.005 | 1.192 | 1.277 | 2.700 | 4.853 | 2.789 | 2.684 | 2.546 | 2.398 | 2.209 |
18 | 0.751 | 0.988 | 1.172 | 1.255 | 2.647 | 2.789 | 4.828 | 2.689 | 2.546 | 2.399 | 2.210 |
19 | 0.725 | 0.953 | 1.130 | 1.210 | 2.553 | 2.684 | 2.689 | 4.619 | 2.498 | 2.349 | 2.165 |
20 | 0.688 | 0.904 | 1.072 | 1.148 | 2.421 | 2.546 | 2.546 | 2.498 | 4.284 | 2.266 | 2.085 |
21 | 0.648 | 0.851 | 1.009 | 1.081 | 2.280 | 2.398 | 2.399 | 2.349 | 2.266 | 3.937 | 2.004 |
22 | 0.597 | 0.784 | 0.930 | 0.996 | 2.100 | 2.209 | 2.210 | 2.165 | 2.085 | 2.004 | 3.515 |
23 | 0.554 | 0.728 | 0.863 | 0.924 | 1.949 | 2.050 | 2.051 | 2.010 | 1.936 | 1.857 | 1.760 |
24 | 0.502 | 0.659 | 0.782 | 0.837 | 1.767 | 1.858 | 1.859 | 1.822 | 1.755 | 1.684 | 1.593 |
25 | 0.477 | 0.627 | 0.742 | 0.795 | 1.677 | 1.764 | 1.764 | 1.729 | 1.666 | 1.599 | 1.512 |
26 | 0.440 | 0.577 | 0.684 | 0.733 | 1.546 | 1.625 | 1.626 | 1.594 | 1.535 | 1.474 | 1.394 |
27 | 0.393 | 0.516 | 0.611 | 0.655 | 1.381 | 1.452 | 1.453 | 1.424 | 1.372 | 1.317 | 1.246 |
28 | 0.369 | 0.484 | 0.574 | 0.615 | 1.296 | 1.363 | 1.363 | 1.336 | 1.287 | 1.236 | 1.169 |
29 | 0.372 | 0.487 | 0.576 | 0.617 | 1.300 | 1.367 | 1.367 | 1.340 | 1.290 | 1.238 | 1.171 |
30 | 6.432 | 8.424 | 9.97 | 10.67 | 22.48 | 23.62 | 23.62 | 23.15 | 22.29 | 21.40 | 20.24 |
g′ = 23 | 24 | 25 | 26 | 27 | 28 | 29 | 30 | |
---|---|---|---|---|---|---|---|---|
g = 12 | 0.554 | 0.502 | 0.477 | 0.440 | 0.393 | 0.369 | 0.372 | 6.432 |
13 | 0.728 | 0.659 | 0.627 | 0.577 | 0.516 | 0.484 | 0.487 | 8.424 |
14 | 0.863 | 0.782 | 0.742 | 0.684 | 0.611 | 0.574 | 0.576 | 9.968 |
15 | 0.924 | 0.837 | 0.795 | 0.733 | 0.655 | 0.615 | 0.617 | 10.67 |
16 | 1.949 | 1.767 | 1.677 | 1.546 | 1.381 | 1.296 | 1.300 | 22.48 |
17 | 2.050 | 1.858 | 1.764 | 1.625 | 1.452 | 1.363 | 1.367 | 23.62 |
18 | 2.051 | 1.859 | 1.764 | 1.626 | 1.453 | 1.363 | 1.367 | 23.62 |
19 | 2.010 | 1.822 | 1.729 | 1.594 | 1.424 | 1.336 | 1.340 | 23.15 |
20 | 1.936 | 1.755 | 1.666 | 1.535 | 1.372 | 1.287 | 1.290 | 22.29 |
21 | 1.857 | 1.684 | 1.599 | 1.474 | 1.317 | 1.236 | 1.238 | 21.40 |
22 | 1.760 | 1.593 | 1.512 | 1.394 | 1.246 | 1.169 | 1.171 | 20.24 |
23 | 3.177 | 1.521 | 1.440 | 1.328 | 1.187 | 1.114 | 1.116 | 19.28 |
24 | 1.521 | 2.792 | 1.358 | 1.249 | 1.117 | 1.048 | 1.049 | 18.13 |
25 | 1.440 | 1.358 | 2.604 | 1.214 | 1.082 | 1.016 | 1.017 | 17.58 |
26 | 1.328 | 1.249 | 1.214 | 2.349 | 1.037 | 0.971 | 0.972 | 16.79 |
27 | 1.187 | 1.117 | 1.082 | 1.037 | 2.039 | 0.913 | 0.912 | 15.76 |
28 | 1.114 | 1.048 | 1.016 | 0.971 | 0.913 | 1.885 | 0.888 | 15.30 |
29 | 1.116 | 1.049 | 1.017 | 0.972 | 0.912 | 0.888 | 1.891 | 15.39 |
30 | 19.28 | 18.13 | 17.58 | 16.79 | 15.76 | 15.30 | 15.39 | 429.6 |
(239Pu) | (240Pu) | (69Ga) | (71Ga) | (C) | (1H) | |
---|---|---|---|---|---|---|
(239Pu) | Max. value = at g = 30, g′ = 30 | Max. value = at g = 30, g′ = 30 | Max. value = at g = 23, g′ = 23 | Max. value = at g = 22, g′ = 22 | Max. value = at g = 30, g′ = 30 | Max. value = at g = 30, g′ = 30 |
(240Pu) | Max. value = at g = 27, g′ = 27 | Max. value = at g = 23, g′ = 23 | Max. value = at g = 23, g′ = 23 | Max. value = at g = 27, g′ = 30 | Max. value = at g = 27, g′ = 30 | |
(69Ga) | Max. value = at g = 23, g′ = 23 | Max. value = at g = 23, g′ = 23 | Max. value = at g = 23, g′ = 30 | Max. value = at g = 23, g′ = 30 | ||
(71Ga) | Max. value = at g = 23, g′ = 23 | Max. value = at g = 22, g′ = 30 | Max. value = at g = 22, g′ = 30 | |||
(C) | Max. value = at g = 30, g′ = 30 | Max. value = at g = 30, g′ = 30 | ||||
(1H) | Max. value = at g = 30, g′ = 30 |
g | 1st-Order | 2nd-Order | g | 1st-Order | 2nd-Order |
---|---|---|---|---|---|
1 | −1.145 × 10−7 | 3.249 × 10−11 | 16 | −1.512 × 10−2 | 1.311 × 10−3 |
2 | −2.510 × 10−7 | 7.767 × 10−11 | 17 | −1.135 × 10−2 | 1.532 × 10−3 |
3 | −7.830 × 10−7 | 2.614 × 10−10 | 18 | −1.292 × 10−2 | 3.234 × 10−3 |
4 | −3.514 × 10−6 | 1.145 × 10−9 | 19 | −1.869 × 10−2 | 8.442 × 10−3 |
5 | −6.145 × 10−6 | 7.800 × 10−10 | 20 | −2.455 × 10−2 | 1.517 × 10−2 |
6 | −8.015 × 10−6 | 5.749 × 10−10 | 21 | −2.750 × 10−2 | 1.944 × 10−2 |
7 | −1.775 × 10−4 | 1.004 × 10−7 | 22 | −2.859 × 10−2 | 2.457 × 10−2 |
8 | −2.526 × 10−4 | 2.144 × 10−7 | 23 | −2.366 × 10−2 | 1.772 × 10−2 |
9 | −5.375 × 10−4 | 8.957 × 10−7 | 24 | −2.307 × 10−2 | 2.485 × 10−2 |
10 | −9.783 × 10−4 | 2.918 × 10−6 | 25 | −2.158 × 10−2 | 1.776 × 10−2 |
11 | −1.422 × 10−3 | 6.334 × 10−6 | 26 | −2.143 × 10−2 | 1.813 × 10−2 |
12 | −4.660 × 10−3 | 5.717 × 10−5 | 27 | −2.082 × 10−3 | 3.127 × 10−4 |
13 | −1.059 × 10−2 | 3.400 × 10−4 | 28 | −1.019 × 10−3 | 1.715 × 10−4 |
14 | −1.400 × 10−2 | 7.416 × 10−4 | 29 | −1.369 × 10−2 | 1.128 × 10−2 |
15 | −1.244 × 10−2 | 8.073 × 10−4 | 30 | −1.275 × 10−1 | 1.034 × 10−1 |
g | 1st-Order | 2nd-Order | g | 1st-Order | 2nd-Order |
---|---|---|---|---|---|
1 | −2.499 × 10−9 | 1.547 × 10−14 | 16 | −1.452 × 10−3 | 1.209 × 10−5 |
2 | −6.870 × 10−9 | 5.819 × 10−14 | 17 | −1.084 × 10−3 | 1.396 × 10−5 |
3 | −2.428 × 10−8 | 2.514 × 10−13 | 18 | −9.294 × 10−4 | 1.674 × 10−5 |
4 | −1.600 × 10−7 | 2.374 × 10−12 | 19 | −6.621 × 10−4 | 1.060 × 10−5 |
5 | −1.281 × 10−6 | 3.388 × 10−11 | 20 | −8.618 × 10−4 | 1.870 × 10−5 |
6 | −5.753 × 10−6 | 2.962 × 10−10 | 21 | −1.314 × 10−3 | 4.439 × 10−5 |
7 | −7.137 × 10−5 | 1.624 × 10−8 | 22 | −1.412 × 10−3 | 5.995 × 10−5 |
8 | −1.268 × 10−4 | 5.397 × 10−8 | 23 | −3.226 × 10−3 | 3.294 × 10−4 |
9 | −2.568 × 10−4 | 2.044 × 10−7 | 24 | −2.543 × 10−3 | 3.020 × 10−4 |
10 | −4.359 × 10−4 | 5.795 × 10−7 | 25 | −5.821 × 10−4 | 1.293 × 10−5 |
11 | −5.226 × 10−4 | 8.551 × 10−7 | 26 | −1.575 × 10−4 | 9.800 × 10−7 |
12 | −1.043 × 10−3 | 2.866 × 10−6 | 27 | −1.610 × 10−2 | 1.871 × 10−2 |
13 | −1.050 × 10−3 | 3.345 × 10−6 | 28 | −8.986 × 10−3 | 1.333 × 10−2 |
14 | −1.021 × 10−3 | 3.944 × 10−6 | 29 | −1.362 × 10−4 | 1.117 × 10−6 |
15 | −9.080 × 10−4 | 4.304 × 10−6 | 30 | −7.881 × 10−3 | 3.950 × 10−4 |
g | 1st-Order | 2nd-Order | g | 1st-Order | 2nd-Order |
---|---|---|---|---|---|
1 | −2.053 × 10−10 | 1.045 × 10−16 | 16 | −2.138 × 10−5 | 2.622 × 10−9 |
2 | −4.744 × 10−10 | 2.775 × 10−16 | 17 | −1.513 × 10−5 | 2.723 × 10−9 |
3 | −1.419 × 10−9 | 8.586 × 10−16 | 18 | −1.502 × 10−5 | 4.373 × 10−9 |
4 | −4.719 × 10−9 | 2.064 × 10−15 | 19 | −1.756 × 10−5 | 7.451 × 10−9 |
5 | −2.376 × 10−8 | 1.166 × 10−14 | 20 | −3.435 × 10−5 | 2.970 × 10−8 |
6 | −1.515 × 10−7 | 2.055 × 10−13 | 21 | −5.491 × 10−5 | 7.751 × 10−8 |
7 | −2.325 × 10−6 | 1.722 × 10−11 | 22 | −3.027 × 10−5 | 2.754 × 10−8 |
8 | −3.489 × 10−6 | 4.088 × 10−11 | 23 | −5.698 × 10−5 | 1.027 × 10−7 |
9 | −5.361 × 10−6 | 8.912 × 10−11 | 24 | −2.286 × 10−7 | 2.441 × 10−12 |
10 | −7.098 × 10−6 | 1.536 × 10−10 | 25 | −1.674 × 10−7 | 1.068 × 10−12 |
11 | −8.740 × 10−6 | 2.392 × 10−10 | 26 | −7.901 × 10−7 | 2.465 × 10−11 |
12 | −1.955 × 10−5 | 1.006 × 10−9 | 27 | −6.411 × 10−7 | 2.964 × 10−11 |
13 | −2.104 × 10−5 | 1.343 × 10−9 | 28 | −3.406 × 10−8 | 1.916 × 10−13 |
14 | −2.032 × 10−5 | 1.563 × 10−9 | 29 | −4.347 × 10−8 | 1.138 × 10−13 |
15 | −1.554 × 10−5 | 1.261 × 10−9 | 30 | −4.118 × 10−6 | 1.078 × 10−10 |
g | 1st-Order | 2nd-Order | g | 1st-Order | 2nd-Order |
---|---|---|---|---|---|
1 | −1.839 × 10−10 | 8.383 × 10−17 | 16 | −1.352 × 10−5 | 1.049 × 10−9 |
2 | −4.168 × 10−10 | 2.142 × 10−16 | 17 | −1.060 × 10−5 | 1.335 × 10−9 |
3 | −1.109 × 10−9 | 5.240 × 10−16 | 18 | −9.678 × 10−6 | 1.815 × 10−9 |
4 | −3.183 × 10−9 | 9.395 × 10−16 | 19 | −1.486 × 10−5 | 5.341 × 10−9 |
5 | −1.094 × 10−8 | 2.474 × 10−15 | 20 | −1.847 × 10−5 | 8.588 × 10−9 |
6 | −5.001 × 10−8 | 2.238 × 10−14 | 21 | −1.537 × 10−5 | 6.075 × 10−9 |
7 | −7.874 × 10−7 | 1.976 × 10−12 | 22 | −7.731 × 10−5 | 1.796 × 10−7 |
8 | −1.330 × 10−6 | 5.941 × 10−12 | 23 | −7.778 × 10−5 | 1.914 × 10−7 |
9 | −2.120 × 10−6 | 1.393 × 10−11 | 24 | −4.854 × 10−7 | 1.100 × 10−11 |
10 | −2.885 × 10−6 | 2.538 × 10−11 | 25 | −3.219 × 10−7 | 3.953 × 10−12 |
11 | −3.616 × 10−6 | 4.095 × 10−11 | 26 | −1.465 × 10−6 | 8.478 × 10−11 |
12 | −8.943 × 10−6 | 2.106 × 10−10 | 27 | −1.173 × 10−6 | 9.917 × 10−11 |
13 | −1.100 × 10−5 | 3.669 × 10−10 | 28 | −6.199 × 10−8 | 6.345 × 10−13 |
14 | −1.263 × 10−5 | 6.039 × 10−10 | 29 | −7.896 × 10−8 | 3.754 × 10−13 |
15 | −1.069 × 10−5 | 5.968 × 10−10 | 30 | −7.472 × 10−6 | 3.550 × 10−10 |
g | 1st-Order | 2nd-Order | g | 1st-Order | 2nd-Order |
---|---|---|---|---|---|
1 | −9.934 × 10−10 | 1.050 × 10−14 | 16 | −8.425 × 10−7 | 2.335 × 10−12 |
2 | −1.106 × 10−9 | 6.574 × 10−15 | 17 | −4.651 × 10−7 | 7.633 × 10−13 |
3 | −2.539 × 10−9 | 1.254 × 10−14 | 18 | −3.363 × 10−7 | 4.193 × 10−13 |
4 | −1.657 × 10−8 | 1.185 × 10−13 | 19 | −3.362 × 10−7 | 4.366 × 10−13 |
5 | −9.586 × 10−8 | 8.498 × 10−13 | 20 | −4.126 × 10−7 | 6.841 × 10−13 |
6 | −1.736 × 10−7 | 1.014 × 10−12 | 21 | −5.639 × 10−7 | 1.333 × 10−12 |
7 | −5.044 × 10−7 | 1.744 × 10−12 | 22 | −8.195 × 10−7 | 2.969 × 10−12 |
8 | −4.619 × 10−7 | 1.439 × 10−12 | 23 | −1.250 × 10−6 | 7.274 × 10−12 |
9 | −5.906 × 10−7 | 1.917 × 10−12 | 24 | −1.868 × 10−6 | 1.735 × 10−11 |
10 | −6.247 × 10−7 | 2.024 × 10−12 | 25 | −2.907 × 10−6 | 4.382 × 10−11 |
11 | −6.212 × 10−7 | 1.978 × 10−12 | 26 | −4.402 × 10−6 | 1.068 × 10−10 |
12 | −1.187 × 10−6 | 4.715 × 10−12 | 27 | −6.457 × 10−6 | 2.489 × 10−10 |
13 | −1.082 × 10−6 | 4.132 × 10−12 | 28 | −9.842 × 10−6 | 6.094 × 10−10 |
14 | −9.096 × 10−7 | 3.135 × 10−12 | 29 | −1.559 × 10−5 | 1.555 × 10−9 |
15 | −6.998 × 10−7 | 2.011 × 10−12 | 30 | −5.560 × 10−4 | 1.514 × 10−6 |
g | 1st-Order | 2nd-Order | g | 1st-Order | 2nd-Order |
---|---|---|---|---|---|
1 | −4.006 × 10−10 | 1.708 × 10−15 | 16 | −9.360 × 10−6 | 2.882 × 10−10 |
2 | −8.966 × 10−10 | 4.318 × 10−15 | 17 | −1.556 × 10−5 | 8.540 × 10−10 |
3 | −2.775 × 10−9 | 1.498 × 10−14 | 18 | −2.450 × 10−5 | 2.227 × 10−9 |
4 | −1.425 × 10−8 | 8.766 × 10−14 | 19 | −3.837 × 10−5 | 5.686 × 10−9 |
5 | −7.512 × 10−8 | 5.218 × 10−13 | 20 | −5.974 × 10−5 | 1.434 × 10−8 |
6 | −2.434 × 10−7 | 1.993 × 10−12 | 21 | −9.248 × 10−5 | 3.584 × 10−8 |
7 | −1.549 × 10−6 | 1.645 × 10−11 | 22 | −1.403 × 10−4 | 8.706 × 10−8 |
8 | −1.542 × 10−6 | 1.604 × 10−11 | 23 | −2.144 × 10−4 | 2.139 × 10−7 |
9 | −1.983 × 10−6 | 2.160 × 10−11 | 24 | −3.206 × 10−4 | 5.108 × 10−7 |
10 | −2.070 × 10−6 | 2.222 × 10−11 | 25 | −4.992 × 10−4 | 1.292 × 10−6 |
11 | −2.001 × 10−6 | 2.052 × 10−11 | 26 | −7.564 × 10−4 | 3.153 × 10−6 |
12 | −3.647 × 10−6 | 4.455 × 10−11 | 27 | −1.110 × 10−3 | 7.350 × 10−6 |
13 | −3.321 × 10−6 | 3.889 × 10−11 | 28 | −1.691 × 10−3 | 1.800 × 10−5 |
14 | −3.244 × 10−6 | 3.988 × 10−11 | 29 | −2.680 × 10−3 | 4.591 × 10−5 |
15 | −3.479 × 10−6 | 4.972 × 10−11 | 30 | −9.557 × 10−2 | 4.473 × 10−2 |
Relative Standard Deviation | 10% | 5% | 1% |
---|---|---|---|
Relative Standard Deviation | 10% | 5% | 1% |
---|---|---|---|
© 2019 by the authors. Licensee MDPI, Basel, Switzerland. This article is an open access article distributed under the terms and conditions of the Creative Commons Attribution (CC BY) license (http://creativecommons.org/licenses/by/4.0/).
Share and Cite
Cacuci, D.G.; Fang, R.; Favorite, J.A. Comprehensive Second-Order Adjoint Sensitivity Analysis Methodology (2nd-ASAM) Applied to a Subcritical Experimental Reactor Physics Benchmark: I. Effects of Imprecisely Known Microscopic Total and Capture Cross Sections. Energies 2019, 12, 4219. https://doi.org/10.3390/en12214219
Cacuci DG, Fang R, Favorite JA. Comprehensive Second-Order Adjoint Sensitivity Analysis Methodology (2nd-ASAM) Applied to a Subcritical Experimental Reactor Physics Benchmark: I. Effects of Imprecisely Known Microscopic Total and Capture Cross Sections. Energies. 2019; 12(21):4219. https://doi.org/10.3390/en12214219
Chicago/Turabian StyleCacuci, Dan G., Ruixian Fang, and Jeffrey A. Favorite. 2019. "Comprehensive Second-Order Adjoint Sensitivity Analysis Methodology (2nd-ASAM) Applied to a Subcritical Experimental Reactor Physics Benchmark: I. Effects of Imprecisely Known Microscopic Total and Capture Cross Sections" Energies 12, no. 21: 4219. https://doi.org/10.3390/en12214219
APA StyleCacuci, D. G., Fang, R., & Favorite, J. A. (2019). Comprehensive Second-Order Adjoint Sensitivity Analysis Methodology (2nd-ASAM) Applied to a Subcritical Experimental Reactor Physics Benchmark: I. Effects of Imprecisely Known Microscopic Total and Capture Cross Sections. Energies, 12(21), 4219. https://doi.org/10.3390/en12214219