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
Abstract
:1. Introduction
2. Computation of 1st- and 2nd-Order Sensitivities of the PERP Leakage Response to Fission Cross Sections
2.1. First-Order Sensitivities
2.2. Second-Order Sensitivities
2.3. Numerical Results for
2.3.1. Second-Order Unmixed Relative Sensitivities
2.3.2. Second-Order Relative Sensitivities
3. Mixed Second-Order Sensitivities of the PERP Total Leakage Response with Respect to the Parameters Underlying the Benchmark’s Fission and Total Cross Sections
3.1. Computing the Second-Order Sensitivities
3.2. Alternative Path: Computing the Second-Order Sensitivities
3.3. Numerical Results for
3.3.1. Second-Order Relative Sensitivities
3.3.2. Second-Order Relative Sensitivities
3.3.3. Second-Order Relative Sensitivities
4. Mixed Second-Order Sensitivities of the PERP Total Leakage Response with Respect to the Parameters Underlying the Benchmark’s Fission and Scattering Cross Sections
4.1. Computing the Second-Order Sensitivities
- (1)
- where the quantities refer to the parameters underlying the fission microscopic cross sections, while the quantities refer to the parameters underlying the 0th-order scattering microscopic cross sections; and
- (2)
- where the quantities refer to the parameters underlying the fission microscopic cross sections, and the quantities refer to the parameters underlying the -order () scattering microscopic cross sections.
4.1.1. Second-Order Sensitivities
4.1.2. Second-Order Sensitivities
4.2. Alternative Path: Computing the Second-Order Sensitivities
- (1)
- , where the quantities refer to the parameters underlying the 0th-order scattering cross sections, while the quantities refer to the parameters underlying the fission cross sections;
- (2)
- , where the quantities refer to the parameters underlying the -order () scattering cross sections, and the quantities refer to the parameters underlying the fission cross sections.
4.2.1. Second-Order Sensitivities
4.2.2. Second-Order Sensitivities
4.3. Numerical Results for
4.3.1. Results for the Relative Sensitivities
4.3.2. Results for the Relative Sensitivities
4.3.3. Results for the Relative Sensitivities
4.3.4. Results for the Relative Sensitivities
5. Computation of the 1st- and 2nd-Order Sensitivities of the PERP Leakage Response to the Average Number of Neutrons Per Fission
5.1. First-Order Sensitivities
5.2. Second-Order Sensitivities
5.3. Numerical Results for
5.3.1. Second-Order Unmixed Relative Sensitivities
5.3.2. Second-Order Relative Sensitivities
6. Mixed Second-Order Sensitivities of the PERP Total Leakage Response with Respect to the Parameters Underlying the Average Number of Neutrons Per Fission and Total Cross Sections
6.1. Second-Order Sensitivities
6.2. Alternative Path: Computing the Second-Order Sensitivities
6.3. Numerical Results for
6.3.1. Second-Order Relative Sensitivities
6.3.2. Second-Order Relative Sensitivities
6.3.3. Second-Order Relative Sensitivities
6.3.4. Second-Order Relative Sensitivities
7. Mixed Second-Order Sensitivities of the PERP Total Leakage Response with Respect to the Parameters Underlying the Average Number of Neutrons Per Fission and Scattering Cross Sections
7.1. Computation of the Second-Order Sensitivities
- (1)
- , where the quantities enumerate the parameters underlying the average number of neutrons per fission, and the quantities enumerate parameters underlying the 0th-order scattering microscopic cross sections;
- (2)
- , where the quantities enumerate the parameters underlying the average number of neutrons per fission, and the quantities enumerate parameters underlying the -order () scattering microscopic cross sections.
7.1.1. Computation of the Second-Order Sensitivities
7.1.2. Second-Order Sensitivities
7.2. Alternative Path: Computing the Second-Order Sensitivities
- (1)
- , where the quantities refer to the parameters underlying the 0th-order scattering cross sections, while the quantities refer to the parameters underlying the average number of neutrons per fission;
- (2)
- , where the quantities refer to the parameters underlying the -order () scattering cross sections, and the quantities refer to the parameters underlying the average number of neutrons per fission.
7.2.1. Second-Order Sensitivities
7.2.2. Second-Order Sensitivities
7.3. Numerical Results for
7.3.1. Results for the Relative Sensitivities
7.3.2. Results for the Relative Sensitivities
7.3.3. Results for the Relative Sensitivities
7.3.4. Results for the Relative Sensitivities
8. Mixed Second-Order Sensitivities of the PERP Total Leakage Response with Respect to the Parameters Underlying the Average Number of Neutrons per Fission and Fission Cross Sections
8.1. Computing the Second-Order Sensitivities
8.2. Alternative Path: Computing the Second-Order Sensitivities
8.3. Numerical Results for
9. Quantification of Uncertainties in the PERP Leakage Response Due to Uncertainties in Fission Cross Sections
10. Uncertainties in the PERP Leakage Response Stemming from Uncertainties in the Average Number of Neutrons per Fission
11. Conclusions
- The 1st-order relative sensitivities of the PERP leakage response with respect to the group-averaged microscopic fission cross sections for the two fissionable PERP isotopes are positive, as shown in Table 2 and Table 3, signifying that an increase in will cause an increase in the PERP leakage response (i.e., more neutrons will leak out of the sphere). The 2nd-order unmixed relative sensitivities of the PERP leakage response with respect to the group-averaged microscopic fission cross sections are positive for the energy groups , but are negative for the other energy groups;
- Comparing the results for the 1st-order relative sensitivities to those obtained for the 2nd-order unmixed relative sensitivities for isotope 1 (239Pu) indicates that the values of the 2nd-order sensitivities are close to, and generally smaller than, the corresponding values of the 1st-order sensitivities for the same energy group, except for the 12th energy group, where the 2nd-order relative sensitivity is larger. For isotope 2 (240Pu), the values for both the 1st- and 2nd-order relative sensitivities are very small, and the values of the 2nd-order unmixed relative sensitivities are at least an order of magnitude smaller than the corresponding values of the 1st-order ones. The largest values of the 1st-order and 2nd-order relative sensitivities are always related to the 12th energy group for both isotopes 239Pu and 240Pu;
- The 1st-order relative sensitivities with respect to the fission cross sections are up to 50% smaller than the corresponding values with respect to the total cross sections, and are approximately one order of magnitude larger than the corresponding 1st-order relative sensitivities with respect to the 0th-order scattering cross sections for isotope 239Pu. Likewise, the absolute values of the 2nd-order unmixed relative sensitivities with respect to the fission cross sections are 50–90% smaller than the corresponding values with respect to total cross sections but are approximately one to two orders of magnitudes larger than the 2nd-order sensitivities corresponding to the 0th-order scattering cross sections for 239Pu;
- The 2nd-order mixed sensitivities are mostly positive. Among the elements in the matrix , 11 elements have relative sensitivities greater than 1.0. All of these 11 large sensitivities belong to the submatrix , and involve the 12th energy group of the fission cross sections of isotope 239Pu; the largest of these sensitivities is . The values of the mixed 2nd-order relative sensitivities involving the fission cross sections of isotope 240Pu are all smaller than 1.0;
- The 2nd-order mixed sensitivities are mostly negative. Among the elements of the matrix , 84 elements belonging to the submatrices , and have absolute values greater than 1.0. These 84 large sensitivities involve the fission cross sections of isotope 239Pu, and the total cross sections of isotopes 239Pu, C and 1H. The largest (negative) relative sensitivity is . The mixed 2nd-order relative sensitivities involving the fission cross sections of the isotope 240Pu or the total cross sections of isotopes 240Pu, 69Ga and 71Ga have absolute values smaller than 1.0;
- The dimensional matrix comprises more elements having positive (rather than negative) values when involving even-orders () scattering cross sections, and vice-versa when involving odd-orders () scattering cross sections. Overall, however, the total number of positive elements in this matrix is comparable to that of negative elements in the sensitivity matrix. As shown in Table 8, Table 9, Table 10 and Table 11, in each submatrix of , the largest absolute values of the 2nd-order relative sensitivities corresponding to even-order scattering parameters are all positive, while those corresponding to odd-orders scattering parameters are all negative;
- The absolute values of all the elements of the matrix are less than 1.0, and the vast majority of them are very small; also, the higher the order of scattering cross sections, the smaller the absolute values of these sensitivities. Also, it is observed that the largest absolute value of the 2nd-order relative sensitivities in each submatrix of , generally involve the fission cross sections for the 12th energy group of isotopes 239Pu or240Pu, and the self-scattering cross sections in the 12th or 7th energy group for all isotopes. The largest sensitivity comprised in is , i.e., the 2nd-order mixed sensitivity of the PERP leakage response with respect to the 12th energy group of the fission and 0th-order self-scattering cross sections of isotope 239Pu;
- The alternative paths for computing the mixed 2nd-order sensitivities, which are due to the symmetry of these sensitivities, provide multiple reciprocal “solution verifications” possibilities, ensuring that the respective computations were performed correctly. However, one of the alternative paths is much more efficient computationally than the other. For example, computing is around 3 times more efficient than computing alternatively the symmetric sensitivities . Also, computing is about 60 times more efficient than computing alternatively the sensitivities ;
- Many mixed 2nd-order sensitivities of the leakage response to the group-averaged fission and total microscopic cross sections are significantly larger than the unmixed 2nd-order sensitivities of the leakage response with respect to the group-averaged fission microscopic cross sections. Therefore, it would be very important to obtain correlations among the various model parameter, since the correlations among the respective fission and total cross sections could provide significantly larger contributions to the response moments than the standard deviations of the fission cross sections.
- 10.
- The 1st-order relative sensitivities of for the two fissionable PERP isotopes are positive, as shown in Table 13 and Table 14, signifying that an increase in will cause an increase in the PERP leakage response . The 2nd-order unmixed relative sensitivities of the leakage response with respect to the average number of neutrons per fission are also positive;
- 11.
- Comparing the results for the 1st-order relative sensitivities of to those 2nd-order unmixed relative sensitivities for isotope 1 (239Pu) indicate that, for energy groups the values of the 2nd-order unmixed sensitivities are significantly larger than the corresponding values of the 1st-order sensitivities for the same energy group, and they are smaller for other energy groups. For isotope 2 (240Pu), the values for both the 1st- and 2nd-order relative sensitivities are all very small, and the values of the 2nd-order unmixed relative sensitivities are at least an order of magnitude smaller than the corresponding values of the 1st-order ones. The largest values of the 1st-order and 2nd-order unmixed relative sensitivities are always related to the 12th energy group of the parameters underlying the average number of neutrons per fission for both isotopes 239Pu and 240Pu;
- 12.
- The 1st-order relative sensitivities of are comparable to the corresponding values with respect to the total cross sections for energy groups , but for energy groups , they are considerably smaller. On the other hand, the 1st-order relative sensitivities of are 30% to 50% larger than the corresponding values to for 239Pu. Likewise, the values of the 2nd-order unmixed relative sensitivities with respect to the average number of neutrons per fission are significantly smaller than the corresponding values with respect to total cross sections, but larger than the corresponding values with respect to fission cross sections;
- 13.
- The 2nd-order mixed sensitivities are all positive. Among the elements in the matrix , 52 elements have relative sensitivities greater than 1.0. All of these 52 large sensitivities belong to the submatrix , and involve the parameters underlying the average number of neutrons per fission of isotope 239Pu. The largest of these sensitivities is . The values of the mixed 2nd-order relative sensitivities involving the parameters underlying the average number of neutrons per fission of isotope 240Pu are all smaller than 1.0;
- 14.
- The 2nd-order mixed sensitivities are mostly negative. Among the elements of the matrix , there are 179 elements belonging to the submatrices , and which have absolute values greater than 1.0; 178 of these large sensitivities involve the parameters underlying the average number of neutrons per fission of isotope 239Pu, and the total cross sections of isotopes 239Pu, C and 1H. The largest (negative) relative sensitivity is . In addition, the mixed 2nd-order relative sensitivities involving isotopes 240Pu, 69Ga and 71Ga generally have absolute values smaller than 1.0;
- 15.
- The dimensional matrix comprises more elements having positive (rather than negative) values for even-orders () scattering cross sections and vice-versa when involving odd-orders () scattering cross sections. Overall, however, this matrix contains about as many positive elements as negative ones. As shown in Table 21, Table 22, Table 23 and Table 24, in each submatrix of , the largest absolute values of the 2nd-order relative sensitivities corresponding to even-order scattering parameters are all positive, while those corresponding to odd-orders scattering parameters are all negative;
- 16.
- The absolute values of all the elements of the matrix are less than 1.0, and the vast majority of them are very small; also, the higher the order of scattering cross sections, the smaller the absolute values of these sensitivities. Furthermore, it is observed that in each submatrix of the largest 2nd-order relative sensitivities generally involve for the 12th energy group of isotopes 239Pu or240Pu, and the self-scattering cross sections in the 12th or 7th energy group for all isotopes. The largest 2nd-order sensitivity comprised in is ;
- 17.
- The 2nd-order mixed sensitivities are mostly positive. Among the elements in the matrix , 28 elements have relative sensitivities greater than 1.0. All of these 28 large sensitivities belong to the submatrix , and relate to the average number of neutrons per fission of isotope 239Pu. The largest of these sensitivities is . The values of the mixed 2nd-order relative sensitivities involving isotope 240Pu are all smaller than 1.0;
- 18.
- Many mixed 2nd-order relative sensitivities in the matrices , and are significantly larger than the unmixed 2nd-order sensitivities of the leakage response with respect to the parameters underlying the average number of neutrons per fission. Therefore, it would be very important to obtain correlations among the average number of neutrons per fission, total and fission cross sections, so that significantly larger contributions from those mixed sensitivities to the response moments can be accounted for.
Author Contributions
Acknowledgments
Conflicts of Interest
Appendix A. Definitions of PERP Model Parameters
Appendix B
Nomenclature
Symbols | |
adjoint operator | |
, | parameters used in Watt’s fission spectra approximation for isotope |
forward operator | |
boundary of energy group | |
expected value of the leakage response taking into account contributions from the uncorrelated parameters , where can be , respectively | |
2nd-order contributions to the expected value due to uncorrelated parameters of , where can be , respectively | |
fraction of isotope decays that are spontaneous fission events | |
parameters in vector indexed by and | |
total number of energy groups | |
total 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 | |
variable for the order of Legendre-expansion of the microscopic scattering cross sections, | |
total neutron leakage from the PERP sphere | |
total number of materials | |
total number of fissionable isotopes | |
atom number density for isotope and material | |
Legendre and associated Legendre polynomials appropriate for the geometry under consideration | |
source term in group | |
spatial variable | |
external radius of the PERP benchmark | |
outer surface of the PERP sphere | |
standard deviation associated with the model parameter | |
standard deviation associated with the model parameter | |
parameters in vector indexed by and | |
parameters in vector indexed by and | |
2nd-level adjoint functions in group at point in direction associated with the fission parameter indexed by (e.g., ) | |
zeroth order 2nd-level adjoint flux moments in group at point , | |
order 2nd-level adjoint flux moments in group at point | |
variance of the leakage response taking into account contributions solely from the uncorrelated and normally-distributed parameters , where can be , respectively | |
first-order contributions to the variance | |
second-order contributions to the variance | |
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 scattering cross sections | |
vector of imprecisely known fission cross sections | |
vector of imprecisely known parameters underlying the average number of neutrons per fission | |
vector of imprecisely known atom number densities | |
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 | |
the skewness due to the variances of parameters in the leakage response, where can be , respectively | |
Kronecker-delta functionals | |
2nd-level adjoint functions in group at point in direction associated with the scattering cross section parameter indexed by (e.g., ) | |
zeroth order 2nd-level adjoint flux moments in group at point , and | |
decay constant for isotope | |
third-order moment of the leakage response with contributions solely from the uncorrelated and normally-distributed parameters , where can be , respectively | |
number of neutrons produced per fission by isotope and energy group | |
the spontaneous emission of an average neutrons of an isotope | |
zeroth order of adjoint flux moment in group at point | |
order adjoint flux moment in group at point , | |
zeroth order moments for and | |
order 2nd-level adjoint flux moments in group at point | |
cross sections | |
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 | |
zeroth order of forward flux moment in group at point | |
order forward flux moment in group at point , | |
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 | |
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 | |
, | order of Legendre expansion associated with the microscopic scattering cross section parameters indexed by (e.g., ) or (e.g., ) |
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 | |
first-order contributions from uncorrelated and normally-distributed parameters | |
2nd-order contributions from uncorrelated parameters | |
2nd-order contributions from uncorrelated and normally-distributed parameters | |
uncorrelated and normally-distributed parameters | |
Abbreviations | |
1st-Level adjoint sensitivity system | |
second-order adjoint sensitivity analysis methodology | |
2nd-Level adjoint sensitivity system | |
order of the finite expansion in Legendre polynomial | |
polyethylene-reflected plutonium |
References
- 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. accepted for publication.
- 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. accepted for publication.
- Mattingly, J. Polyethylene-Reflected Plutonium Metal Sphere: Subcritical Neutron and Gamma Measurements; SAND2009-5804 Rev. 3; Sandia National Laboratories: Albuquerque, NM, USA, July 2012. [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 (Revised Nov. 2008); Los Alamos National Laboratories: Los Alamos, NM, USA.
- 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]
- 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. LA-UR-02-1839. [Google Scholar]
- Conlin, J.L.; Parsons, D.K.; Gardiner, S.J.; Gray, M.G.; Lee, M.B.; White, M.C. MENDF71X: Multigroup Neutron Cross-Section Data Tables Based upon ENDF/B-VII.1X; LA-UR-15-29571 (7 October 2013); Los Alamos National Laboratories: Los Alamos, NM, USA. [CrossRef]
- Chadwick, M.B.; Herman, M.; Obložinský, P.; Dunn, M.E.; Danon, Y.; Kahler, A.C.; Smith, D.L.; Pritychenko, B.; Arbanas, G.; Arcilla, 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]
- 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: IV. Effects of Imprecisely Known Source Parameters. Energies. under review.
- 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. (under review).
Isotopes | k = 1 (239Pu) | k = 2 (240Pu) |
---|---|---|
i = 1 (239Pu) | 11 elements with absolute values > 1.0 | Max. value = 6.97 × 10−2 at g = 12, g′ = 12 |
i = 2 (240Pu) | Max. value = 6.97 × 10−2 at g = 12, g′ = 12 | Max. value = 3.60 × 10−3 at g = 12, g′ = 12 |
g | 1st-Order | 2nd-Order | g | 1st-Order | 2nd-Order |
---|---|---|---|---|---|
1 | 0.00039 | −0.00016 | 16 | 0.197 | −0.001 |
2 | 0.00080 | −0.00033 | 17 | 0.075 | −0.023 |
3 | 0.00231 | −0.00091 | 18 | 0.042 | −0.018 |
4 | 0.011 | −0.0038 | 19 | 0.036 | −0.019 |
5 | 0.050 | −0.014 | 20 | 0.036 | −0.025 |
6 | 0.129 | −0.008 | 21 | 0.033 | −0.031 |
7 | 0.585 | 0.559 | 22 | 0.029 | −0.029 |
8 | 0.489 | 0.353 | 23 | 0.025 | −0.029 |
9 | 0.589 | 0.536 | 24 | 0.024 | −0.019 |
10 | 0.612 | 0.580 | 25 | 0.020 | −0.025 |
11 | 0.569 | 0.487 | 26 | 0.019 | −0.024 |
12 | 0.882 | 1.348 | 27 | 0.017 | −0.011 |
13 | 0.611 | 0.584 | 28 | 0.010 | −0.003 |
14 | 0.393 | 0.188 | 29 | 0.014 | −0.016 |
15 | 0.222 | 0.023 | 30 | 0.131 | −0.153 |
g | 1st-Order | 2nd-Order | g | 1st-Order | 2nd-Order |
---|---|---|---|---|---|
1 | 2.642 × 10−5 | −6.237 × 10−7 | 16 | 6.361 × 10−4 | −5.532 × 10−9 |
2 | 4.790 × 10−5 | −1.173 × 10−6 | 17 | 2.769 × 10−4 | −3.154 × 10−7 |
3 | 1.350 × 10−4 | −3.098 × 10−6 | 18 | 1.399 × 10−4 | −1.919 × 10−7 |
4 | 6.524 × 10−4 | −1.461 × 10−5 | 19 | 7.740 × 10−5 | −8.545 × 10−8 |
5 | 3.138 × 10−3 | −5.479 × 10−5 | 20 | 1.254 × 10−4 | −3.111 × 10−7 |
6 | 7.612 × 10−3 | −3.207 × 10−5 | 21 | 6.055 × 10−5 | −1.048 × 10−7 |
7 | 3.300 × 10−2 | 1.771 × 10−3 | 22 | 5.724 × 10−6 | −1.080 × 10−9 |
8 | 2.796 × 10−2 | 1.150 × 10−3 | 23 | 3.435 × 10−6 | −5.246 × 10−10 |
9 | 3.210 × 10−2 | 1.584 × 10−3 | 24 | 9.157 × 10−7 | −2.867 × 10−11 |
10 | 3.229 × 10−2 | 1.600 × 10−3 | 25 | 2.862 × 10−6 | −4.747 × 10−10 |
11 | 2.868 × 10−2 | 1.226 × 10−3 | 26 | 4.661 × 10−8 | −1.384 × 10−13 |
12 | 4.568 × 10−2 | 3.602 × 10−3 | 27 | 5.471 × 10−6 | −1.214 × 10−9 |
13 | 1.904 × 10−2 | 5.649 × 10−4 | 28 | 7.800 × 10−6 | −2.129 × 10−9 |
14 | 3.365 × 10−3 | 1.359 × 10−5 | 29 | 1.965 × 10−8 | −3.219 × 10−14 |
15 | 8.900 × 10−4 | 3.629 × 10−7 | 30 | 7.126 × 10−7 | −4.394 × 10−12 |
Groups | g′ = 6 | 7 | 8 | 9 | 10 | 11 | 12 | 13 | 14 |
---|---|---|---|---|---|---|---|---|---|
g = 6 | −0.008 | 0.163 | 0.136 | 0.163 | 0.170 | 0.158 | 0.244 | 0.169 | 0.109 |
7 | 0.163 | 0.558 | 0.609 | 0.732 | 0.762 | 0.707 | 1.095 | 0.758 | 0.488 |
8 | 0.136 | 0.609 | 0.353 | 0.607 | 0.633 | 0.589 | 0.911 | 0.631 | 0.406 |
9 | 0.163 | 0.732 | 0.607 | 0.536 | 0.758 | 0.707 | 1.095 | 0.757 | 0.487 |
10 | 0.170 | 0.762 | 0.633 | 0.758 | 0.580 | 0.732 | 1.137 | 0.787 | 0.506 |
11 | 0.158 | 0.707 | 0.589 | 0.707 | 0.732 | 0.487 | 1.054 | 0.731 | 0.470 |
12 | 0.244 | 1.095 | 0.911 | 1.095 | 1.137 | 1.054 | 1.348 | 1.130 | 0.728 |
13 | 0.169 | 0.758 | 0.631 | 0.757 | 0.787 | 0.731 | 1.130 | 0.584 | 0.502 |
14 | 0.109 | 0.488 | 0.406 | 0.487 | 0.506 | 0.470 | 0.728 | 0.502 | 0.188 |
Isotopes | ||||||
---|---|---|---|---|---|---|
(239Pu) | 35 elements with absolute values > 1.0 | Min. value = at g = 12, g′ = 12 | Min. value = at g = 12, g′ = 12 | Min. value = at g = 12, g′ = 12 | 1 element with absolute value > 1.0 | 48 elements with absolute values > 1.0 |
(240Pu) | Min. value = at g = 12, g′ = 12 | Min. value = at g = 12, g′ = 12 | Min. value = at g = 12, g′ = 12 | Min. value = at g = 12, g′ = 12 | Min. value = at g = 12, g′ = 30 | Min. value = at g = 12, g′ = 30 |
Groups | g′ = 6 | 7 | 8 | 9 | 10 | 11 | 12 | 13 | 14 | 15 | 16 |
---|---|---|---|---|---|---|---|---|---|---|---|
g = 6 | −0.091 | −0.199 | −0.183 | −0.213 | −0.213 | −0.195 | −0.332 | −0.291 | −0.241 | −0.176 | −0.200 |
7 | −0.159 | −1.189 | −0.821 | −0.955 | −0.958 | −0.876 | −1.488 | −1.302 | −1.080 | −0.787 | −0.895 |
8 | −0.131 | −0.758 | −0.921 | −0.790 | −0.796 | −0.729 | −1.238 | −1.083 | −0.898 | −0.654 | −0.743 |
9 | −0.157 | −0.908 | −0.844 | −1.229 | −0.953 | −0.876 | −1.487 | −1.302 | −1.079 | −0.786 | −0.893 |
10 | −0.164 | −0.941 | −0.868 | −1.015 | −1.263 | −0.906 | −1.546 | −1.352 | −1.121 | −0.816 | −0.927 |
11 | −0.152 | −0.875 | −0.804 | −0.935 | −0.946 | −1.086 | −1.431 | −1.257 | −1.041 | −0.758 | −0.861 |
12 | −0.236 | −1.361 | −1.250 | −1.452 | −1.455 | −1.342 | −2.630 | −1.941 | −1.611 | −1.174 | −1.331 |
13 | −0.164 | −0.946 | −0.870 | −1.010 | −1.013 | −0.926 | −1.588 | −1.685 | −1.110 | −0.811 | −0.919 |
14 | −0.105 | −0.610 | −0.562 | −0.653 | −0.654 | −0.599 | −1.021 | −0.905 | −0.981 | −0.516 | −0.592 |
15 | −0.059 | −0.345 | −0.318 | −0.369 | −0.370 | −0.339 | −0.577 | −0.510 | −0.434 | −0.464 | −0.325 |
Groups | g′ = 15 | 16 | 17 | 18 | 19 | 20 | 21 | 22 | 29 | 30 |
---|---|---|---|---|---|---|---|---|---|---|
g = 5 | −0.048 | −0.099 | −0.102 | −0.100 | −0.096 | −0.091 | −0.085 | −0.078 | −0.048 | −0.833 |
6 | −0.123 | −0.252 | −0.258 | −0.253 | −0.244 | −0.231 | −0.217 | −0.199 | −0.122 | −2.114 |
7 | −0.550 | −1.128 | −1.157 | −1.135 | −1.093 | −1.034 | −0.972 | −0.892 | −0.548 | −9.472 |
8 | −0.457 | −0.936 | −0.960 | −0.942 | −0.907 | −0.858 | −0.806 | −0.740 | −0.455 | −7.859 |
9 | −0.548 | −1.124 | −1.152 | −1.130 | −1.088 | −1.030 | −0.967 | −0.888 | −0.546 | −9.431 |
10 | −0.568 | −1.164 | −1.193 | −1.170 | −1.127 | −1.067 | −1.002 | −0.920 | −0.565 | −9.768 |
11 | −0.525 | −1.077 | −1.104 | −1.083 | −1.042 | −0.987 | −0.927 | −0.851 | −0.523 | −9.038 |
12 | −0.809 | −1.658 | −1.699 | −1.667 | −1.605 | −1.519 | −1.427 | −1.311 | −0.805 | −13.92 |
13 | −0.555 | −1.137 | −1.165 | −1.143 | −1.100 | −1.042 | −0.979 | −0.899 | −0.552 | −9.549 |
14 | −0.351 | −0.725 | −0.742 | −0.728 | −0.701 | −0.664 | −0.623 | −0.573 | −0.352 | −6.087 |
15 | −0.197 | −0.404 | −0.415 | −0.407 | −0.392 | −0.371 | −0.348 | −0.320 | −0.197 | −3.405 |
16 | −0.200 | −0.382 | −0.365 | −0.359 | −0.345 | −0.327 | −0.307 | −0.282 | −0.174 | −3.010 |
17 | −0.081 | −0.169 | −0.170 | −0.136 | −0.131 | −0.124 | −0.117 | −0.107 | −0.067 | −1.151 |
18 | −0.049 | −0.103 | −0.109 | −0.112 | −0.075 | −0.071 | −0.067 | −0.062 | −0.038 | −0.665 |
Isotopes | ||||||
---|---|---|---|---|---|---|
(239Pu) | Max. value = at g = 12, g′ = 12 → h = 12 | Max. value = at g = 12, g′ = 12 → h = 12 | Max. value = at g = 12, g′ = 12 → h = 12 | Max. value = at g = 12, g′ = 12 → h = 12 | Max. value = at g = 12, g′ = 12 → h = 12 | Max. value = at g = 12, g′ = 16 → h = 17 |
(240Pu) | Max. value = at g = 12, g′ = 12 → h = 12 | Max. value = at g = 12, g′ = 12 → h = 12 | Max. value = at g = 12, g′ = 12 → h = 12 | Max. value = at g = 12, g′ = 12 → h = 12 | Max. value = at g = 12, g′ = 12 → h = 12 | Max. value = at g = 12, g′ = 16 → h = 17 |
Isotopes | ||||||
---|---|---|---|---|---|---|
(239Pu) | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 12 → h = 12 | Min. value = at g = 12, g′ = 12 → h = 12 |
(240Pu) | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 12 → h = 12 | Min. value = at g = 12, g′ = 12 → h = 12 |
Isotopes | ||||||
---|---|---|---|---|---|---|
(239Pu) | Max. value = at g = 12, g′ = 7 → h = 7 | Max. value = at g = 12, g′ = 7 → h = 7 | Max. value = at g = 12, g′ = 7 → h = 7 | Max. value = at g = 12, g′ = 7 → h = 7 | Max. value = at g = 12, g′ = 7 → h = 7 | Max. value = at g = 12, g′ = 12 → h = 12 |
(240Pu) | Max. value = at g = 12, g′ = 7 → h = 7 | Max. value = at g = 12, g′ = 7 → h = 7 | Max. value = at g = 12, g′ = 7 → h = 7 | Max. value = at g = 12, g′ = 7 → h = 7 | Max. value = at g = 12, g′ = 7 → h = 7 | Max. value = at g = 12, g′ = 12 → h = 12 |
Isotopes | ||||||
---|---|---|---|---|---|---|
(239Pu) | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 12 → h = 12 |
(240Pu) | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 12 → h = 12 |
Isotopes | ||
---|---|---|
(239Pu) | 52 elements with absolute values > 1.0 | Max. value = at g = 12, g′ = 12 |
(240Pu) | Max. value = at g = 12, g′ = 12 | Max. value = at g = 12, g′ = 12 |
g | 1st-Order | 2nd-Order | g | 1st-Order | 2nd-Order |
---|---|---|---|---|---|
1 | 0.0005266 | 0.0000006 | 16 | 0.297 | 0.177 |
2 | 0.0010690 | 0.0000025 | 17 | 0.117 | 0.027 |
3 | 0.0030646 | 0.0000206 | 18 | 0.068 | 0.009 |
4 | 0.0140 | 0.0004 | 19 | 0.060 | 0.007 |
5 | 0.0672 | 0.0097 | 20 | 0.065 | 0.009 |
6 | 0.169 | 0.060 | 21 | 0.071 | 0.010 |
7 | 0.762 | 1.192 | 22 | 0.064 | 0.008 |
8 | 0.659 | 0.880 | 23 | 0.064 | 0.008 |
9 | 0.802 | 1.299 | 24 | 0.042 | 0.004 |
10 | 0.843 | 1.430 | 25 | 0.055 | 0.006 |
11 | 0.786 | 1.243 | 26 | 0.051 | 0.005 |
12 | 1.215 | 2.963 | 27 | 0.026 | 0.001 |
13 | 0.847 | 1.444 | 28 | 0.012 | 0.0003 |
14 | 0.555 | 0.620 | 29 | 0.034 | 0.002 |
15 | 0.321 | 0.208 | 30 | 0.461 | 0.429 |
g | 1st-Order | 2nd-Order | g | 1st-Order | 2nd-Order |
---|---|---|---|---|---|
1 | 3.278 × 10−5 | 2.395 × 10−9 | 16 | 9.569 × 10−4 | 1.834 × 10−6 |
2 | 6.388 × 10−5 | 9.027 × 10−9 | 17 | 4.337 × 10−4 | 3.745 × 10−7 |
3 | 1.790 × 10−4 | 7.043 × 10−8 | 18 | 2.251 × 10−4 | 1.009 × 10−7 |
4 | 8.648 × 10−4 | 1.627 × 10−6 | 19 | 1.278 × 10−4 | 3.261 × 10−8 |
5 | 4.197 × 10−3 | 3.767 × 10−5 | 20 | 2.292 × 10−4 | 1.050 × 10−7 |
6 | 1.003 × 10−2 | 2.115 × 10−4 | 21 | 1.298 × 10−4 | 3.374 × 10−8 |
7 | 4.313 × 10−2 | 3.819 × 10−3 | 22 | 1.227 × 10−5 | 3.019 × 10−10 |
8 | 3.774 × 10−2 | 2.890 × 10−3 | 23 | 8.578 × 10−6 | 1.480 × 10−10 |
9 | 4.397 × 10−2 | 3.904 × 10−3 | 24 | 1.631 × 10−6 | 5.347 × 10−12 |
10 | 4.475 × 10−2 | 4.034 × 10−3 | 25 | 7.522 × 10−6 | 1.140 × 10−10 |
11 | 3.985 × 10−2 | 3.192 × 10−3 | 26 | 1.225 × 10−7 | 3.010 × 10−14 |
12 | 6.316 × 10−2 | 8.011 × 10−3 | 27 | 8.661 × 10−6 | 1.505 × 10−10 |
13 | 2.649 × 10−2 | 1.411 × 10−3 | 28 | 9.563 × 10−6 | 1.845 × 10−10 |
14 | 4.768 × 10−3 | 4.572 × 10−5 | 29 | 4.853 × 10−8 | 4.752 × 10−15 |
15 | 1.289 × 10−3 | 3.338 × 10−6 | 30 | 2.463 × 10−6 | 1.222 × 10−11 |
Groups | g′ = 6 | 7 | 8 | 9 | 10 | 11 | 12 | 13 | 14 | 15 |
---|---|---|---|---|---|---|---|---|---|---|
g = 6 | 0.060 | 0.267 | 0.230 | 0.279 | 0.293 | 0.273 | 0.422 | 0.294 | 0.193 | 0.112 |
7 | 0.267 | 1.192 | 1.024 | 1.244 | 1.306 | 1.217 | 1.879 | 1.312 | 0.860 | 0.497 |
8 | 0.230 | 1.024 | 0.880 | 1.069 | 1.122 | 1.046 | 1.615 | 1.127 | 0.739 | 0.427 |
9 | 0.279 | 1.244 | 1.069 | 1.299 | 1.363 | 1.271 | 1.962 | 1.370 | 0.897 | 0.519 |
10 | 0.293 | 1.306 | 1.122 | 1.363 | 1.430 | 1.333 | 2.059 | 1.437 | 0.942 | 0.545 |
11 | 0.273 | 1.217 | 1.046 | 1.271 | 1.333 | 1.243 | 1.919 | 1.340 | 0.878 | 0.508 |
12 | 0.422 | 1.879 | 1.615 | 1.962 | 2.059 | 1.919 | 2.963 | 2.068 | 1.356 | 0.784 |
13 | 0.294 | 1.312 | 1.127 | 1.370 | 1.437 | 1.340 | 2.068 | 1.444 | 0.946 | 0.547 |
14 | 0.193 | 0.860 | 0.739 | 0.897 | 0.942 | 0.878 | 1.356 | 0.946 | 0.620 | 0.359 |
15 | 0.112 | 0.497 | 0.427 | 0.519 | 0.545 | 0.508 | 0.784 | 0.547 | 0.359 | 0.208 |
Isotopes | ||||||
---|---|---|---|---|---|---|
(239Pu) | 72 elements with absolute values > 1.0 | Min. value = at g = 12, g′ = 12 | Min. value = at g = 12, g′ = 12 | Min. value = at g = 12, g′ = 12 | 7 elements with absolute values > 1.0 | 99 elements with absolute values > 1.0 |
(240Pu) | Min. value = at g = 12, g′ = 12 | Min. value = at g = 12, g′ = 12 | Min. value = at g = 12, g′ = 12 | Min. value = at g = 12, g′ = 12 | Min. value = at g = 12, g′ = 30 | 1 element with absolute value > 1.0 |
Groups | g′ = 6 | 7 | 8 | 9 | 10 | 11 | 12 | 13 | 14 | 15 | 16 |
---|---|---|---|---|---|---|---|---|---|---|---|
g = 6 | −0.139 | −0.256 | −0.236 | −0.274 | −0.274 | −0.251 | −0.426 | −0.373 | −0.310 | −0.226 | −0.257 |
7 | −0.202 | −1.635 | −1.051 | −1.220 | −1.222 | −1.119 | −1.901 | −1.666 | −1.382 | −1.008 | −1.146 |
8 | −0.172 | −0.997 | −1.334 | −1.049 | −1.051 | −0.962 | −1.634 | −1.432 | −1.188 | −0.866 | −0.985 |
9 | −0.209 | −1.207 | −1.124 | −1.787 | −1.277 | −1.169 | −1.986 | −1.740 | −1.444 | −1.053 | −1.197 |
10 | −0.220 | −1.262 | −1.165 | −1.363 | −1.856 | −1.226 | −2.084 | −1.826 | −1.515 | −1.105 | −1.257 |
11 | −0.205 | −1.178 | −1.083 | −1.259 | −1.275 | −1.612 | −1.942 | −1.702 | −1.413 | −1.030 | −1.171 |
12 | −0.316 | −1.825 | −1.677 | −1.948 | −1.953 | −1.802 | −3.785 | −2.629 | −2.181 | −1.590 | −1.809 |
13 | −0.221 | −1.279 | −1.176 | −1.366 | −1.369 | −1.252 | −2.148 | −2.513 | −1.523 | −1.110 | −1.263 |
14 | −0.145 | −0.840 | −0.773 | −0.898 | −0.900 | −0.825 | −1.406 | −1.247 | −1.565 | −0.728 | −0.828 |
15 | −0.084 | −0.486 | −0.448 | −0.521 | −0.522 | −0.478 | −0.815 | −0.719 | −0.613 | −0.821 | −0.479 |
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 = 30 g′ = 30 |
---|---|---|---|---|---|---|---|
Values | −1.022 | −1.070 | −1.122 | −1.046 | −1.617 | −1.129 | −1.258 |
Groups | g′ = 13 | 14 | 15 | 16 | 17 | 18 | 19 | 20 | 21 |
---|---|---|---|---|---|---|---|---|---|
g = 5 | −0.054 | −0.061 | −0.063 | −0.130 | −0.134 | −0.131 | −0.126 | −0.120 | −0.112 |
6 | −0.134 | −0.153 | −0.158 | −0.325 | −0.333 | −0.327 | −0.315 | −0.298 | −0.280 |
7 | −0.600 | −0.682 | −0.707 | −1.451 | −1.488 | −1.460 | −1.406 | −1.331 | −1.251 |
8 | −0.517 | −0.587 | −0.608 | −1.248 | −1.280 | −1.256 | −1.209 | −1.145 | −1.076 |
9 | −0.628 | −0.714 | −0.740 | −1.518 | −1.557 | −1.528 | −1.471 | −1.393 | −1.308 |
10 | −0.660 | −0.750 | −0.777 | −1.593 | −1.634 | −1.603 | −1.543 | −1.461 | −1.373 |
11 | −0.615 | −0.699 | −0.724 | −1.486 | −1.523 | −1.495 | −1.439 | −1.362 | −1.280 |
12 | −0.950 | −1.080 | −1.118 | −2.295 | −2.352 | −2.308 | −2.223 | −2.104 | −1.977 |
13 | −0.691 | −0.754 | −0.781 | −1.602 | −1.643 | −1.612 | −1.552 | −1.470 | −1.381 |
14 | −0.448 | −0.524 | −0.512 | −1.050 | −1.077 | −1.057 | −1.018 | −0.964 | −0.906 |
15 | −0.260 | −0.299 | −0.323 | −0.609 | −0.624 | −0.613 | −0.590 | −0.559 | −0.525 |
16 | −0.246 | −0.282 | −0.295 | −0.629 | −0.580 | −0.569 | −0.548 | −0.519 | −0.488 |
17 | −0.103 | −0.119 | −0.125 | −0.261 | −0.293 | −0.227 | −0.219 | −0.208 | −0.195 |
18 | −0.064 | −0.074 | −0.078 | −0.165 | −0.174 | −0.195 | −0.130 | −0.123 | −0.116 |
19 | −0.057 | −0.067 | −0.071 | −0.150 | −0.158 | −0.159 | −0.180 | −0.108 | −0.102 |
20 | −0.063 | −0.074 | −0.078 | −0.165 | −0.174 | −0.175 | −0.172 | −0.197 | −0.111 |
21 | −0.069 | −0.081 | −0.086 | −0.181 | −0.191 | −0.191 | −0.188 | −0.182 | −0.211 |
22 | −0.062 | −0.073 | −0.078 | −0.163 | −0.172 | −0.172 | −0.169 | −0.163 | −0.157 |
23 | −0.063 | −0.074 | −0.079 | −0.166 | −0.174 | −0.174 | −0.171 | −0.165 | −0.158 |
24 | −0.042 | −0.049 | −0.052 | −0.110 | −0.115 | −0.115 | −0.113 | −0.109 | −0.104 |
25 | −0.054 | −0.064 | −0.068 | −0.142 | −0.149 | −0.149 | −0.146 | −0.140 | −0.135 |
26 | −0.051 | −0.059 | −0.063 | −0.132 | −0.139 | −0.139 | −0.136 | −0.131 | −0.125 |
27 | −0.026 | −0.031 | −0.033 | −0.069 | −0.073 | −0.072 | −0.071 | −0.068 | −0.065 |
28 | −0.012 | −0.014 | −0.015 | −0.031 | −0.033 | −0.033 | −0.032 | −0.031 | −0.030 |
29 | −0.035 | −0.041 | −0.043 | −0.091 | −0.095 | −0.095 | −0.093 | −0.089 | −0.085 |
30 | −0.470 | −0.550 | −0.584 | −1.224 | −1.281 | −1.278 | −1.250 | −1.201 | −1.151 |
Groups | g′ = 22 | 23 | 24 | 25 | 26 | 27 | 28 | 29 | 30 |
---|---|---|---|---|---|---|---|---|---|
g = 5 | −0.103 | −0.095 | −0.086 | −0.082 | −0.076 | −0.067 | −0.063 | −0.063 | −1.096 |
6 | −0.257 | −0.238 | −0.215 | −0.204 | −0.188 | −0.168 | −0.157 | −0.158 | −2.732 |
7 | −1.148 | −1.063 | −0.962 | −0.913 | −0.841 | −0.750 | −0.703 | −0.706 | −12.20 |
8 | −0.988 | −0.915 | −0.828 | −0.785 | −0.724 | −0.645 | −0.605 | −0.607 | −10.49 |
9 | −1.202 | −1.113 | −1.007 | −0.955 | −0.880 | −0.785 | −0.736 | −0.739 | −12.77 |
10 | −1.261 | −1.167 | −1.056 | −1.002 | −0.924 | −0.823 | −0.772 | −0.775 | −13.39 |
11 | −1.176 | −1.088 | −0.985 | −0.934 | −0.861 | −0.767 | −0.720 | −0.723 | −12.49 |
12 | −1.816 | −1.681 | −1.521 | −1.443 | −1.330 | −1.186 | −1.112 | −1.116 | −19.29 |
13 | −1.268 | −1.174 | −1.063 | −1.008 | −0.929 | −0.828 | −0.777 | −0.780 | −13.48 |
14 | −0.832 | −0.770 | −0.697 | −0.661 | −0.609 | −0.543 | −0.509 | −0.512 | −8.843 |
15 | −0.482 | −0.447 | −0.404 | −0.383 | −0.353 | −0.315 | −0.295 | −0.297 | −5.129 |
16 | −0.448 | −0.415 | −0.376 | −0.357 | −0.329 | −0.293 | −0.275 | −0.276 | −4.777 |
17 | −0.180 | −0.167 | −0.151 | −0.143 | −0.132 | −0.118 | −0.111 | −0.111 | −1.921 |
18 | −0.107 | −0.099 | −0.090 | −0.085 | −0.078 | −0.070 | −0.066 | −0.066 | −1.142 |
19 | −0.094 | −0.087 | −0.079 | −0.075 | −0.069 | −0.062 | −0.058 | −0.058 | −1.004 |
20 | −0.102 | −0.095 | −0.086 | −0.082 | −0.075 | −0.067 | −0.063 | −0.063 | −1.096 |
21 | −0.111 | −0.103 | −0.093 | −0.089 | −0.082 | −0.073 | −0.069 | −0.069 | −1.190 |
22 | −0.183 | −0.093 | −0.084 | −0.080 | −0.073 | −0.065 | −0.062 | −0.062 | −1.068 |
23 | −0.151 | −0.179 | −0.085 | −0.080 | −0.074 | −0.066 | −0.062 | −0.062 | −1.077 |
24 | −0.099 | −0.095 | −0.113 | −0.053 | −0.049 | −0.043 | −0.041 | −0.041 | −0.708 |
25 | −0.127 | −0.122 | −0.116 | −0.144 | −0.063 | −0.056 | −0.053 | −0.053 | −0.915 |
26 | −0.118 | −0.113 | −0.107 | −0.104 | −0.129 | −0.052 | −0.049 | −0.049 | −0.849 |
27 | −0.062 | −0.059 | −0.055 | −0.054 | −0.052 | −0.064 | −0.025 | −0.026 | −0.443 |
28 | −0.028 | −0.027 | −0.025 | −0.024 | −0.023 | −0.022 | −0.028 | −0.012 | −0.200 |
29 | −0.081 | −0.077 | −0.072 | −0.070 | −0.067 | −0.063 | −0.062 | −0.083 | −0.578 |
30 | −1.085 | −1.031 | −0.967 | −0.936 | −0.893 | −0.836 | −0.811 | −0.817 | −15.02 |
Isotopes | ||||||
---|---|---|---|---|---|---|
(239Pu) | Max. value = at g = 12, g′ = 12 → h = 12 | Max. value = at g = 12, g′ = 12 → h = 12 | Max. value = at g = 12, g′ = 12 → h = 12 | Max. value = at g = 12, g′ = 12 → h = 12 | Max. value = at g = 12, g′ = 12 → h = 12 | Max. value = at g = 12, g′ = 16 → h = 17 |
(240Pu) | Max. value = at g = 12, g′ = 12 → h = 12 | Max. value = at g = 12, g′ = 12 → h = 12 | Max. value = at g = 12, g′ = 12 → h = 12 | Max. value = at g = 12, g′ = 12 → h = 12 | Max. value = at g = 12, g′ = 12 → h = 12 | Max. value = at g = 12, g′ = 16 → h = 17 |
Isotopes | ||||||
---|---|---|---|---|---|---|
(239Pu) | Min. value = at g = 12, g′ = 12 → h = 12 | Min. value = at g = 12, g′ = 12 → h = 12 | Min. value = at g = 12, g′ = 12 → h = 12 | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 12 → h = 12 | Min. value = at g = 12, g′ = 12 → h = 12 |
(240Pu) | Min. value = at g = 12, g′ = 12 → h = 12 | Min. value = at g = 12, g′ = 12 → h = 12 | Min. value = at g = 12, g′ = 12 → h = 12 | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 12 → h = 12 | Min. value = at g = 12, g′ = 12 → h = 12 |
Isotopes | ||||||
---|---|---|---|---|---|---|
(239Pu) | Max. value = at g = 12, g′ = 7 → h = 7 | Max. value = at g = 12, g′ = 7 → h = 7 | Max. value = at g = 12, g′ = 7 → h = 7 | Max. value = at g = 12, g′ = 7 → h = 7 | Max. value = at g = 12, g′ = 7 → h = 7 | Max. value = at g = 12, g′ = 12 → h = 12 |
(240Pu) | Max. value = at g = 7, g′ = 7 → h = 7 | Max. value = at g = 7, g′ = 7 → h = 7 | Max. value = at g = 7, g′ = 7 → h = 7 | Max. value = at g = 7, g′ = 7 → h = 7 | Max. value = at g = 7, g′ = 7 → h = 7 | Max. value = at g = 12, g′ = 12 → h = 12 |
Isotopes | ||||||
---|---|---|---|---|---|---|
(239Pu) | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 12 → h = 12 |
(240Pu) | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 7 → h = 7 | Min. value = at g = 7, g′ = 7 → h = 7 | Min. value = at g = 12, g′ = 12 → h = 12 |
Isotopes | ||
---|---|---|
(239Pu) | 28 elements with absolute values > 1.0 | Max. value = at g = 12, g′ = 12 |
(240Pu) | Max. value = at g = 12, g′ = 12 | Max. value = at g = 12, g′ = 12 |
Groups | g′ = 6 | 7 | 8 | 9 | 10 | 11 | 12 | 13 | 14 |
---|---|---|---|---|---|---|---|---|---|
g = 6 | 0.188 | 0.210 | 0.175 | 0.210 | 0.218 | 0.203 | 0.314 | 0.218 | 0.140 |
7 | 0.207 | 1.587 | 0.779 | 0.936 | 0.973 | 0.904 | 1.401 | 0.971 | 0.625 |
8 | 0.179 | 0.801 | 1.227 | 0.804 | 0.836 | 0.776 | 1.203 | 0.834 | 0.537 |
9 | 0.217 | 0.974 | 0.807 | 1.649 | 1.015 | 0.943 | 1.462 | 1.013 | 0.652 |
10 | 0.228 | 1.023 | 0.850 | 1.018 | 1.767 | 0.990 | 1.534 | 1.063 | 0.684 |
11 | 0.212 | 0.953 | 0.793 | 0.952 | 0.986 | 1.577 | 1.430 | 0.991 | 0.638 |
12 | 0.328 | 1.470 | 1.223 | 1.469 | 1.527 | 1.414 | 3.225 | 1.530 | 0.985 |
13 | 0.229 | 1.025 | 0.853 | 1.024 | 1.064 | 0.989 | 1.528 | 1.777 | 0.688 |
14 | 0.150 | 0.671 | 0.558 | 0.670 | 0.697 | 0.647 | 1.002 | 0.691 | 0.910 |
15 | 0.087 | 0.388 | 0.323 | 0.388 | 0.403 | 0.374 | 0.579 | 0.400 | 0.255 |
Relative Standard Deviation | 10% | 5% | 1% |
---|---|---|---|
Relative Standard Deviation | 10% | 5% | 1% |
---|---|---|---|
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Cacuci, D.G.; Fang, R.; Favorite, J.A.; Badea, M.C.; Rocco, F.D. 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. https://doi.org/10.3390/en12214100
Cacuci DG, Fang R, Favorite JA, Badea MC, Rocco FD. 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(21):4100. https://doi.org/10.3390/en12214100
Chicago/Turabian StyleCacuci, D. G., R. Fang, J. A. Favorite, M. C. Badea, and F. Di Rocco. 2019. "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 12, no. 21: 4100. https://doi.org/10.3390/en12214100
APA StyleCacuci, D. G., Fang, R., Favorite, J. A., Badea, M. C., & Rocco, F. D. (2019). 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, 12(21), 4100. https://doi.org/10.3390/en12214100