Abstract
The Second-Order Adjoint Sensitivity Analysis Methodology (2nd-ASAM) is applied to compute the first-order and second-order sensitivities of the leakage response of a polyethylene-reflected plutonium (PERP) experimental system with respect to the following nuclear data: Group-averaged isotopic microscopic fission cross sections, mixed fission/total, fission/scattering cross sections, average number of neutrons per fission (), mixed /total cross sections, /scattering cross sections, and /fission cross sections. The numerical results obtained indicate that the 1st-order relative sensitivities for these nuclear data are smaller than the 1st-order sensitivities of the PERP leakage response with respect to the total cross sections but are larger than those with respect to the scattering cross sections. The vast majority of the 2nd-order unmixed sensitivities are smaller than the corresponding 1st-order ones, but several 2nd-order mixed relative sensitivities are larger than the 1st-order ones. In particular, several 2nd-order sensitivities for 239Pu are significantly larger than the corresponding 1st-order ones. It is also shown that the effects of the 2nd-order sensitivities of the PERP benchmark’s leakage response with respect to the benchmark’s parameters underlying the average number of neutrons per fission, , on the moments (expected value, variance, and skewness) of the PERP benchmark’s leakage response distribution are negligible by comparison to the corresponding effects (on the response distribution) stemming from uncertainties in the total cross sections, but are larger than the corresponding effects (on the response distribution) stemming from uncertainties in the fission and scattering cross sections.
1. Introduction
This work, designated as “Part III,” continues the presentations of results, commenced in Part I [1] and set forth in Part II [2], produced within the ongoing second-order comprehensive sensitivity analysis to nuclear data of the polyethylene-reflected plutonium (PERP) metal sphere benchmark described in [3]. The computational model of the PERP benchmark is solved using the multigroup discrete ordinates neutron transport code PARTISN [4], comprising the following imprecisely known nuclear data parameters: 180 group-averaged total microscopic cross sections, 21,600 group-averaged scattering microscopic cross sections, 120 parameters describing the fission process, 60 parameters describing the fission spectrum, 10 parameters describing the system’s sources, and 6 isotopic number densities.
This work presents the numerical results for the 60 first-order sensitivities of the PERP’s leakage response with respect to the benchmark’s group-averaged fission cross sections, along with the results for the second-order sensitivities of the PERP Benchmark’s leakage response to the group-averaged microscopic fission cross sections, mixed 2nd-order sensitivities to the fission and total microscopic cross sections, and 60 × 21,600 mixed 2nd-order sensitivities to the fission and scattering microscopic cross sections. These sensitivities have been computed by specializing the general expressions derived by Cacuci [5] to the PERP benchmark. Section 2 of this work presents computational results for the 1st-order and 2nd-order sensitivities of the PERP benchmark’s leakage response with respect to the group-averaged microscopic fission cross sections. Section 3 reports numerical results for the matrix of mixed 2nd-order leakage sensitivities to the group-averaged fission and total microscopic cross sections. Section 4 reports numerical results for the matrix of mixed 2nd-order leakage sensitivities to the group-averaged fission and scattering microscopic cross sections.
Section 5 presents computational results for the 60 first-order and second-order unmixed sensitivities of the PERP benchmark’s leakage response with respect to the parameters underlying the average number, , of neutrons per fission. Section 6 reports numerical results for the matrix of mixed 2nd-order leakage sensitivities to and total microscopic cross sections. Section 7 reports numerical results for the 60 × 21,600 matrix of mixed 2nd-order leakage sensitivities to and scattering microscopic cross sections. Section 8 reports numerical results for the matrix of mixed 2nd-order leakage sensitivities to and fission microscopic cross sections.
Section 9 presents the impact of the 1st- and 2nd-order sensitivities on the uncertainties induced in the leakage response by the imprecisely known group-averaged fission microscopic cross section. Section 10 presents the impact of the 1st- and 2nd-order sensitivities on the uncertainties induced in the leakage response by the imprecisely known parameters underlying the average number of neutrons per fission ().
Section 11 concludes this work. The computational results for the sensitivities of the PERP leakage response to the remaining imprecisely known fission spectrum, isotopic atomic number densities, and including the source parameters will be reported in subsequent publications.
2. Computation of 1st- and 2nd-Order Sensitivities of the PERP Leakage Response to Fission Cross Sections
The physical system considered in this work is the same polyethylene-reflected plutonium (acronym: PERP) metal sphere benchmark [3] as was considered in the 2nd-order sensitivity and uncertainty analyses performed for the group-averaged total microscopic cross sections [1] and the group-averaged scattering cross sections [2], respectively. As in [1,2], the neutron flux is computed by solving numerically the neutron transport equation using the PARTISN [4] multigroup discrete ordinates transport code. For the PERP benchmark under consideration, PARTISN [4] solves the following multi-group approximation of the neutron transport equation with a spontaneous fission source provided by the code SOURCES4C [6]:
where denotes the external radius of the PERP benchmark, and where
In Equation (1), the vector denotes the “vector of imprecisely known model parameters”, which has been defined in [1] as , having the vector-components , , , , , and which comprise the various model parameters for the microscopic total cross sections, scattering cross sections, fission cross sections, average number of neutrons per fission, fission spectra, sources, and isotopic number densities, respectively.
The PARTISN [4] calculations used MENDF71X 618-group cross sections [7] collapsed to energy groups, with group boundaries, , as presented in [1]. The MENDF71X library uses ENDF/B-VII.1 Nuclear Data [8].
The total neutron leakage from the PERP sphere, denoted as , will depend (indirectly, through the neutron flux) on all of the imprecisely known model parameters and is defined as follows:
Part I [1] has reported the results for the 1st- and 2nd-order sensitivities of the leakage response with respect to the total and capture microscopic cross sections for and , respectively. Part II [2] has presented the results for the 1st-order sensitivities of the leakage response with respect to the scattering microscopic cross sections and for the 2nd-order sensitivities , and . This work reports the computational results for the 1st-order sensitivities and , and for the 2nd-order sensitivities , , , , , and , and compares these results to those reported in Parts I and II. The components of the vector of model parameters have been defined in [1] and are described in the Appendix A, for convenient reference.
2.1. First-Order Sensitivities
The first-order sensitivity of the PERP leakage response to the group-averaged microscopic fission cross sections, which will be denoted as , comprises two types of contributions. The first type of contributions, which will be denoted as , arises from quantities that involve the macroscopic fission cross sections directly, while the second type of contributions stems indirectly, through the macroscopic total cross sections, which comprise the fission cross sections in their definitions. The contributions are computed using the following particular forms of Equations (152), (156) and (157) in [5]. For convenient referencing, the corresponding equations from [5] used in this work were reproduced in Appendix B.
The multigroup adjoint fluxes appearing in Equation (6) are the solutions of the following 1st-Level Adjoint Sensitivity System (1st-LASS):
where the adjoint operator takes on the following particular form of Equation (149) in [5]:
The second type of contributions, which will be denoted as , includes the contributions stemming from the total cross sections, since the total cross sections comprises the fission cross sections. The contributions are computed using Equation (150) in [5] in conjunction with the relations and , to obtain:
Adding Equations (6) and (10) yields the following expression:
For the PERP benchmark, the cross-sections in every material are treated in the PARTISN [4] calculations as being space-independent within the respective material. When the parameters correspond to the fission cross sections, i.e., , thus the following relations hold:
where the subscripts , and denote the isotope, energy group and material associated with the parameter , respectively; and where and denote the Kronecker-delta functionals (e.g., if ; if ). Inserting Equations (12) and (13) into Equation (11) yields the following expression for computational purposes:
where the flux moments and are defined as follows:
The numerical values of the 1st-order relative sensitivities, , of the leakage response with respect to the fission microscopic cross sections for the six isotopes contained in the PERP benchmark will be presented in Section 2.3, below, in tables that will also include comparisons with the numerical values of the corresponding 2nd-order unmixed relative sensitivities
2.2. Second-Order Sensitivities
The equations needed for deriving the expression of the 2nd-order sensitivities are obtained by particularizing Equations (158), (160), (177) and (179) in [5] to the PERP benchmark. The contribution stemming directly from the fission cross section is obtained by particularizing Equation (179) in [5] to the PERP benchmark, which yields:
where the 2nd-level adjoint functions, and are the solutions of the following 2nd-Level Adjoint Sensitivity System (2nd-LASS) presented in Equations (183)–(185) of [5]:
The parameters and in Equations (17), (18) and (20) correspond to the fission cross sections, and are therefore denoted as and , respectively, where the subscripts and refer to the isotope and energy groups associated with the parameter , respectively, and where the index is defined in Equation (17). Noting that
and inserting the results obtained in Equation (12) and in Equations (22)–(25) into Equations (18), (20) and (17) reduces the latter equation to the following expression:
where
and where the 2nd-level adjoint functions, and are the solutions of the following simplified form of the 2nd-Level Adjoint Sensitivity System (2nd-LASS) shown in Equations (18) and (20):
subject to the boundary conditions shown in Equations (19) and (21), respectively.
The remaining contributions to stem from Equation (158) in [5], which are obtained by using this equation in conjunction with the relations , , and , which gives:
where the 2nd-level adjoint functions and , are the solutions of the following particular form of the 2nd-Level Adjoint Sensitivity System (2nd-LASS) presented in Equations (164)–(166) of [5]:
The expressions of the various derivatives appearing in Equations (31), (32), and (34) are obtained as follows:
where the subscript refers to the material associated with the parameter . Inserting Equations (36), (37) and (13) into Equations (31)–(34) yields the following simplified expression:
where the 2nd-level adjoint functions and , are the solutions of the following simplified 2nd-Level Adjoint Sensitivity System (2nd-LASS):
subject to the boundary conditions shown in Equations (33) and (35), respectively.
Additional contributions stem from Equation (160) in [5], in conjunction with the relation , which takes on the following particular form:
Inserting the results obtained in Equations (23) and (24) into Equation (41), and performing the respective angular integrations, yields the following simplified expression for Equation (41):
where the flux moments and are defined as follows:
Further contributions stem from Equation (177) in [5] in conjunction with the relations and , as follows:
Inserting the results obtained in Equation (37) into Equation (45) reduces the latter to the following expression:
Collecting the partial contributions obtained in Equations (26), (38), (42) and (46), yields the following result:
2.3. Numerical Results for
The 2nd-order absolute sensitivities of the leakage response with respect to the fission cross sections, i.e., , for the fissionable isotopes and energy groups of the PERP benchmark are computed using Equation (47). The (Hessian) matrix of 2nd-order absolute sensitivities has dimensions , since . For convenient comparisons, the numerical results presented in this section are presented in unit-less values of the relative sensitivities that correspond to , which are denoted as and are defined as follows:
The numerical results obtained for the matrix have been partitioned into submatrices, each of dimensions ; the summary of the main features of each submatrix is presented in Table 1. The results for the submatrices are presented in the following form: when a submatrix comprises elements with relative sensitivities with absolute values greater than 1.0, the total number of such elements are counted and shown in the table. Otherwise, if the relative sensitivities of all elements of a submatrix have values lying in the interval , only the element having the largest absolute value in the submatrix is listed in Table 1, together with the phase-space coordinates of that element. The submatrix in Table 1 comprises components with absolute values greater than 1.0; it will therefore be discussed in detail in subsequent sub-sections of this section.
Table 1.
Summary presentation of the matrix .
The 2nd-order mixed sensitivities are mostly positive. Among all the elements in the matrix , a total of 3508 out of 3600 elements have positive values, and most of them are very small, as indicated in Table 1. However, among all the elements, 11 of them have very large relative sensitivities, with values greater than 1.0, as noted in the table. All of these larger sensitivities reside in the sub-matrix , and relate to the fission cross sections in isotope 239Pu. The overall maximum relative sensitivity is . Additional details about the sub-matrix are provided in the following section. Also noted in Table 1 are the results that all of the mixed 2nd-order relative sensitivities involving the fission cross sections of isotope 240Pu (i.e., ) have absolute values smaller than 1.0. The elements with the maximum absolute value in each of the respective submatrices relate to the fission cross sections for the 12th energy group of isotopes 239Pu and 240Pu.
2.3.1. Second-Order Unmixed Relative Sensitivities
The 2nd-order unmixed sensitivities , which are the elements on the diagonal of the matrix , can be directly compared to the values of the 1st-order relative sensitivities , for the leakage response with respect to the fission cross section parameters. These comparisons are presented in Table 2 and Table 3 for the two fissionable isotopes contained in the PERP benchmark. Table 2 compares the 1st-order to the 2nd-order relative sensitivities for isotope 1 (239Pu). This comparison indicates that the values of the 2nd-order sensitivities are comparable 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. The largest values (shown in bold in the table) for the 1st-order and 2nd-order relative sensitivities both related to the 12th energy group of isotope 239Pu. It is noteworthy that all of the 1st-order relative sensitivities are positive, signifying that an increase in will cause an increase in L.
Table 2.
Comparison of 1st-order relative sensitivities and 2nd-order relative sensitivities for isotope 1 (239Pu).
Table 3.
Comparison of 1st-order relative sensitivities and 2nd-order relative sensitivities for isotope 2 (240Pu).
Comparing the corresponding results in Table 2 in this work with Table 5 of Part I [1] and Table 6 of Part II [2] reveals that the absolute values of the 1st-order relative sensitivities with respect to the fission cross sections are significantly smaller than the corresponding 1st-order relative sensitivities with respect to the total cross sections, but they are approximately one order of magnitude larger than the corresponding 1st-order relative sensitivities with respect to the 0th-order self-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 approximately 50–90% smaller than the corresponding 2nd-order unmixed relative sensitivities to the total cross sections, but they are approximately one to two orders of magnitudes larger than the corresponding 2nd-order unmixed relative sensitivities for the 0th-order self-scattering cross sections for isotope 239Pu.
Table 3 presents the results for the 1st-order and 2nd-order unmixed relative sensitivities for isotope 2 (240Pu). These results show that the values for both the 1st- and 2nd-order relative sensitivities are all very small, and the absolute values of the 2nd-order unmixed relative sensitivities are at least one order of magnitude smaller than the corresponding values of the 1st-order ones for all energy groups. The largest 1st-order relative sensitivity is , and the largest 2nd-order unmixed relative sensitivity is ; both occur for the 12th energy group of the fission cross section of 240Pu.
2.3.2. Second-Order Relative Sensitivities
Figure 1 depicts the 2nd-order mixed relative sensitivity results obtained for , , for the leakage response with respect to the fission cross sections of 239Pu. This matrix is symmetrical with respect to its principal diagonal. As shown in Figure 1, the largest 2nd-order relative sensitivities are concentrated in the energy region confined by the energy groups and . The numerical values of these elements are presented in Table 4. Shown in bold in this Table are 11 sensitivities, all involving the 12th energy group of the fission cross sections or of 239Pu, which have values greater than 1.0. The largest value among these sensitivities is attained by the relative 2nd-order unmixed sensitivity . Figure 1 also shows that the majority (877 out of 900) of the elements of have positive 2nd-order relative sensitivities. The remaining 23 elements are located mostly on the diagonal of and have negative values, as presented in Table 2, above.
Figure 1.
The matrix of sensitivities for 239Pu.
Table 4.
Components of having values greater than 1.0.
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
This Section presents the computation and analysis of the numerical results for the 2nd-order mixed sensitivities , of the leakage response with respect to the group-averaged fission and total microscopic cross sections of all isotopes of the PERP benchmark. As has been shown by Cacuci [5], these mixed sensitivities can be computed using two distinct expressions, involving distinct 2nd-level adjoint systems and corresponding adjoint functions, by considering either the computation of or the computation of . These two distinct paths for computing the 2nd-order sensitivities with respect to group-averaged fission and total microscopic cross sections will be presented in Section 3.1 and, respectively, Section 3.2. The end results produced by these two distinct paths must be identical to one another, thus providing a mutual “solution verification” that the respective computations were performed correctly. Moreover, the computational time for these two distinct paths can be much different, and one of them provides the best computational speed, as will be further illustrated by the numerical results presented in Section 3.3.
3.1. Computing the Second-Order Sensitivities
The equations needed for deriving the expression of the 2nd-order sensitivities are obtained by particularizing Equations (158) and (177) in [5] to the PERP benchmark and adding their respective contributions. The expression obtained by particularizing Equation (177) in [5] takes on the following form:
The parameters and in Equation (49) correspond to the fission cross sections and total cross sections, and are therefore denoted as and , respectively. Noting that
and inserting the result obtained in Equation (50) into Equation (49), yields:
The contributions stemming from Equation (158) in [5], in conjunction with the relations and , yields the following expression:
where the adjoint functions and are the solutions of the 2nd-Level Adjoint Sensitivity System (2nd-LASS) as presented in Equations (33), (35), (39)and (40). Noting that
and inserting the results obtained in Equations (53) and (50) into Equation (52), yields:
Combining the partial contributions obtained in Equations (51) and (54), yields the following result:
3.2. Alternative Path: Computing the Second-Order Sensitivities
As mentioned earlier, the mixed 2nd-order sensitivities can also be computed using the alternative expression for . The equations needed for deriving the expression for are obtained by particularizing Equations (158) and (160) in [5] to the PERP benchmark, where Equation (160) provides the direct contributions to the mixed sensitivities , while Equation (158) provides contributions to these sensitivities arising indirectly from the total cross sections. The expression obtained by particularizing Equation (160) in [5] takes the following form:
where the adjoint functions and are the solutions of the 2nd-Level Adjoint Sensitivity System (2nd-LASS) presented in Equations (32), (34), (39) and (40) of Part I [1], which are reproduced below for convenient reference:
The parameters and in Equation (56) correspond to the total cross sections and fission cross sections, and are therefore denoted as and , respectively. Inserting the results obtained in Equations (23) and (24) into Equation (56), yields:
The contributions stemming from Equation (158) in [5], in conjunction with the relations , and , yields:
Noting that
and inserting the results obtained in Equations (37) and (63) into Equation (62), yields:
Adding Equations (61) and (64), yields the following result:
3.3. Numerical Results for
The second-order absolute sensitivities, , of the leakage response with respect to the fission cross sections and the total cross sections for all isotopes of the PERP benchmark have been computed using Equation (55), and have been independently verified by computing using Equation (65). Regarding the computational requirements: Computing needs forward and adjoint PARTISN transport computations for obtaining the adjoint functions and , together with additional forward and adjoint PARTISN computations for obtaining the adjoint functions and . Thus, a total of 120 forward and adjoint PARTISN computations are required to obtain all the adjoint functions needed in Equation (55). In contradistinction, computing would require forward and adjoint PARTISN computations for obtaining the adjoint functions and that are needed in Equation (65). It is thus evident that computing using Equation (55) is 3 times more efficient than computing using Equation (65).
The matrix has dimensions ; corresponding to this matrix is the matrix denoted as of 2nd-order relative sensitivities, which is defined as follows:
To facilitate the presentation and interpretation of the numerical results, the matrix has been partitioned into submatrices, each of dimensions . The summary of the main features of each of these submatrices is presented in Table 5.
Table 5.
Summary presentation of the matrix .
Most of the values of the elements in the matrix are very small, and 10,704 elements out of 10,800 elements have negative values. The results in Table 5 indicate that, when the 2nd-order mixed relative sensitivities involve the fission cross sections of the isotope 240Pu or the total cross sections of isotopes 240Pu, 69Ga and 71Ga, their absolute values are all smaller than 1.0, and the element with the most negative value in each of the submatrices always relates to the fission cross sections for the 12th energy group and the total cross sections for either the 12th energy group or the 30th energy group of the isotopes. There are 84 elements with large relative sensitivities, having values greater than 1.0, as indicated in Table 5. Those large sensitivities reside in the submatrices , and , respectively. All of these 84 large sensitivities involve the fission cross sections of isotope 239Pu, and the total cross sections of isotopes 239Pu, C and 1H. Of the sensitivities summarized in Table 5, the single largest relative value is .
3.3.1. Second-Order Relative Sensitivities
The results obtained for the 2nd-order mixed relative sensitivity of the leakage response with respect to the fission microscopic cross sections of 239Pu and to the total microscopic cross sections of 239Pu, denoted as , are summarized in Table 6 and depicted in Figure 2. Almost all, namely 894 out of 900, elements in this submatrix have negative 2nd-order relative sensitivities; only 6 elements have small positive values. As shown in Figure 2, there are some large 2nd-order mixed relative sensitivities concentrated in the energy region confined by the energy groups and . The actual numerical values of these large elements are presented in Table 6, which comprises 35 elements having values greater than 1.0, as shown in bold in this table. The largest absolute value in this submatrix is attained by the relative 2nd-order mixed sensitivity , which involves the 12th energy group for both the fission and total cross sections of isotope 239Pu.
Table 6.
Components of having values greater than 1.0.
Figure 2.
The matrix of sensitivities for 239Pu.
The absolute values of the mixed sensitivities in row are the largest among all rows, including rows not presented in Table 6. In other words, the absolute value of mixed relative sensitivities involving the fission cross section parameter are always the largest among all groups . Similarly, the values of the mixed sensitivities in group are the most negative among all groups , with one exception for the sensitivity value located in groups and which is less negative than the value located in groups and .
3.3.2. Second-Order Relative Sensitivities
The matrix , comprising the 2nd-order sensitivities of the leakage response with respect to the fission cross sections of isotope 1 (239Pu) and the total cross sections of isotope 5 (C), contains a single large element that has an absolute value greater than 1.0, namely .
3.3.3. Second-Order Relative Sensitivities
The submatrix , comprising the 2nd-order relative sensitivities of the leakage response with respect to the fission microscopic cross sections of isotope 1 (239Pu) and the total microscopic cross sections of isotope 6 (1H), is illustrated in Figure 3. The submatrix includes 48 elements that have absolute values greater than 1.0, as specified, in bold, in Table 7; 35 out of these 48 elements are located in the energy phase-space confined by the energy groups and . The other 13 elements are located in energy groups and . The largest negative value is displayed by the 2nd-order relative sensitivity of the leakage response with respect to the 12th energy group of the fission cross section for 239Pu and the 30th energy group of the total cross section for 1H, namely .
Figure 3.
The matrix of sensitivities .
Table 7.
Elements of , having absolute values greater than 1.0.
As shown in Table 7, the values of the 2nd-order mixed sensitivities involving the fission cross section parameter , in energy group , are the most negative among all energy groups . In addition to the sensitivities presented in Table 7, the following 2nd-order mixed relative sensitivities of the leakage response with respect to the fission microscopic cross sections of 239Pu and the total microscopic cross sections of 1H have absolute values greater than 1.0: , , and .
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
This Section presents the computation and analysis of the numerical results for the 2nd-order mixed sensitivities , of the leakage response with respect to the group-averaged fission and scattering microscopic cross sections of all isotopes of the PERP benchmark. Similarly, the 2nd-order mixed sensitivities can also be computed using the alternative expressions for . These two distinct paths for computing the 2nd-order sensitivities with respect to group-averaged fission and scattering microscopic cross sections will be presented in Section 4.1 and, respectively, Section 4.2 as follows. As will be discussed in detail in Section 4.3, below, the pathway for computing turns out to be 60 times more efficient than the pathway for computing .
4.1. Computing the Second-Order Sensitivities
The equations needed for deriving the expressions of the 2nd-order sensitivities will differ from each other depending on whether the parameter corresponds to the 0th-order scattering cross sections or to the higher-order scattering cross sections, since, as shown in Equation (A3) of Appendix A, the 0th-order scattering cross sections contribute to the total cross sections, while the higher-order ones do not. Therefore, the zeroth order scattering cross sections must be considered separately from the higher order scattering cross sections. As described in [1] and Appendix A, the total number of zeroth-order scattering cross section comprise in is denoted as , where ; and the total number of higher order (i.e., ) scattering cross sections comprised in is denoted as , where , with . There are two distinct cases, as follows:
- (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
The equations needed for deriving the expression of the 2nd-order mixed sensitivities are obtained by particularizing Equations (158), (159), (177) and (178) in [5] to the PERP benchmark, where Equation (178) provides the contributions arising directly form the respective fission and scattering cross sections, while Equations (158), (159) and (177) provide contributions arising indirectly through the total cross sections, since both the fission cross sections and the 0th-order scattering cross sections are part of the total cross sections. The expression obtained by particularizing Equation (178) in [5] to the PERP benchmark yields:
In Equation (67), the parameters indexed by correspond to the fission cross sections, which means that , while the parameters indexed by correspond to the 0th-order scattering cross sections, so that , where the subscripts and refer to the isotope, order of Legendre expansion, and energy groups associated with the parameter , respectively. Noting that
inserting the results obtained in Equations (68) and (69) into Equation (67), using the addition theorem for spherical harmonics in one-dimensional geometry, performing the respective angular integrations, and finally setting in the resulting expression yields the following simplified expression for Equation (67):
where the 0th-order moments , , and have been defined previously in Equations (15), (16), (27) and (28), respectively.
Using Equation (158) in [5] in conjunction with the relations , and yields the following contributions:
where the adjoint functions and are the solutions of the 2nd-Level Adjoint Sensitivity System (2nd-LASS) presented in Equations (33), (35), (39) and (40).
Noting that,
and inserting the results obtained in Equations (72) and (73) into Equation (71), yields the following simplified expression for Equation (71):
Additional contributions stem from Equation (159) in [5], which takes on the following particular form:
Inserting the results obtained in Equations (68) and (69) into Equation (75), using the addition theorem for spherical harmonics in one-dimensional geometry and performing the respective angular integrations, and setting , yields the following simplified expression for Equation (75):
where the 0th-order moments and have been defined previously in Equations (43) and (44), respectively.
Using Equation (177) in [5] in conjunction with the relation yields the final set of contributions, namely:
Replacing the result obtained in Equation (73) into Equation (77) yields the following simplified expression:
Collecting the partial contributions obtained in Equations (70), (74), (76) and (78), yields the following result:
4.1.2. Second-Order Sensitivities
For computing the 2nd-order sensitivities , the parameters correspond to the fission cross sections, and the parameters correspond to the th-order scattering cross sections. In this case, only the fission cross sections contribute to the total cross sections, since the th-order () scattering cross sections are not comprised in the total cross sections. The expression of is obtained by particularizing Equations (159) and (178) in [5] to the PERP benchmark, which yields,
where the first two terms arise from Equation (178) while the last two terms arise from Equations (159). Inserting the results obtained in Equations (68) and (69) into Equation (80), using the addition theorem for spherical harmonics in one-dimensional geometry and performing the respective angular integrations, yields the following expression:
where the moments , , , , and are defined as follows:
4.2. Alternative Path: Computing the Second-Order Sensitivities
The results to be computed using the expressions for obtained in Equations (79) and (81) can be verified, because of the symmetry of the mixed 2nd-order sensitivities, by obtaining the expressions for , which also requires separate consideration of the zeroth-order scattering cross sections. The two cases involved are as follows:
- (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
The equations needed for deriving the expression of the 2nd-order mixed sensitivities are obtained by particularizing Equations (158), (160), (167) and (169) in [5] to the PERP benchmark. The expression obtained by particularizing Equation (169) in [5] to the PERP benchmark is as follows:
where the 2nd-level adjoint functions, and are the solutions of the 2nd-Level Adjoint Sensitivity System (2nd-LASS) presented in Equations (46), (48), (51) and (52) of Part II [2], which are reproduced below for convenient reference:
In Equation (88), the parameters indexed by correspond to the 0th-order scattering cross sections, so that , while the parameters indexed by correspond to the fission cross sections, so that . Inserting the results obtained in Equations (23) and (24) into Equation (88), yields the following simplified expression for Equation (88):
where the 0th-order moments and are defined as follows:
Using Equation (158) in [5] in conjunction with the relations , and yields the following contributions:
where the 2nd-level adjoint functions, and , are the solutions of the 2nd-Level Adjoint Sensitivity System (2nd-LASS) presented in Equations (30), (32), (36) and (37) of Part II [2], which are reproduced below for convenient reference:
Noting that
and inserting the results obtained in Equations (101) and (37) into Equation (96), yields the following simplified expression for Equation (96):
Additional contributions stem from Equation (160) in [5], which takes on the following particular form:
Inserting the results obtained in Equations (23) and (24) into Equation (103), yields the following simplified expression for Equation (103):
Using Equation (167) in [5] in conjunction with the relation yields the following contributions:
Inserting the results obtained in Equation (37) into Equation (105), yields the following simplified expression:
Collecting the partial contributions obtained in Equations (93), (102), (104) and (106), yields the following result:
4.2.2. Second-Order Sensitivities
For this case, only the fission cross sections contribute to the total cross sections, so the parameters correspond to the -order () scattering cross sections, denoted as , and the parameters correspond to the fission cross sections, denoted as . The expression of is obtained by particularizing Equations (167) and (169) in [5] to the PERP benchmark, which yields,
Inserting the results obtained in Equations (23), (24) and (37) into Equation (108), yields the final expression as follows:
4.3. Numerical Results for
Computing the second-order absolute sensitivities, , using Equations (79) and (81) requires forward and adjoint PARTISN computations to obtain the adjoint functions and , as well as forward and adjoint PARTISN computations to obtain the adjoint functions and . Thus, a total of 120 forward and adjoint PARTISN computations are required to obtain all of the 2nd-order sensitivities using Equations (79) and (81).
On the other hand, computing the alternative expression using Equations (107) and (109), requires 7101 forward and adjoint PARTISN computations to obtain the adjoint functions and . The reason for needing “only” 7101, rather than , PARTISN computations is that all of the up-scattering and some of the down-scattering cross sections are zero for the PERP benchmark. Thus, computing using Equations (79) and (81) is about times more efficient than computing by using Equations (107) and (109).
The dimensions of the matrix is , where and . The matrix of 2nd-order relative sensitivities corresponding to , denoted as , is defined as follows:
To facilitate the presentation and interpretation of the numerical results, the matrix has been partitioned into submatrices, each of dimensions . The results for scattering orders , , , and , respectively, are summarized below, in Section 4.3.1, Section 4.3.2, Section 4.3.3 and Section 4.3.4.
4.3.1. Results for the Relative Sensitivities
Table 8 presents the results for 2nd-order relative sensitivities of the leakage response with respect to the fission cross sections and the 0th-order scattering cross sections for all isotopes, , . All of these 2nd-order relative sensitivities are smaller than 1.0. The value of the largest element of each of the respective sub-matrices is presented in Table 8, together with the phase-space coordinates of the respective element. For the 2nd-order mixed sensitivities with respect to the 0th-order scattering cross sections, the values can be positive or negative, but there are more positive values than negative ones. For example, the submatrix , having dimensions , comprises 7577 positive elements, 2563 negative elements, while the remaining elements are zero. The largest absolute values of the mixed 2nd-order sensitivities all involve the fission cross sections for the 12th energy group of isotopes 239Pu or240Pu, and (mostly) the 0th-order self-scattering cross sections in the 12th energy group for isotopes 239Pu, 240Pu, 69Ga, 71Ga andC, or (occasionally) the 0th-order out-scattering cross section for isotope 1H. All of the largest elements in the respective sub-matrix are positive, and the vast majority of them are very small. The overall largest element in the matrix is .
Table 8.
Summary presentation of the matrix .
4.3.2. Results for the Relative Sensitivities
Table 9 summarizes the results for the 2nd-order mixed relative sensitivities of the leakage response with respect to the fission cross sections and the 1st-order scattering cross sections for all isotopes, , . Most of these 2nd-order mixed sensitivities are zero; the non-zero ones are mostly negative. For example, the submatrix , having dimensions , comprises 7798 elements with negative values, 2342 elements with positive values, while the remaining elements are zero. As shown in Table 9, the largest absolute values of the mixed 2nd-order sensitivities all involve the fission cross sections for the 12th energy group of isotopes 239Pu or 240Pu, and either the 1st-order self-scattering cross sections in the 7th energy group for isotopes 239Pu, 240Pu, 69Ga and71Ga, or the 1st-order self-scattering cross sections in the 12th energy group for isotopes C and1H. All of the largest (in absolute value) elements are negative, and the vast majority of them are very small. The overall most negative element in the matrix is .
Table 9.
Summary presentation of the matrix .
4.3.3. Results for the Relative Sensitivities
Table 10 presents the results for the 2nd-order mixed relative sensitivities , , of the leakage response with respect to the fission cross sections and the 2nd-order scattering cross sections for all isotopes. Most of the non-zero elements of are positive. For example, the submatrix , having dimensions , comprises 6308 positive elements and 3832 negative elements, while the remaining elements are zero. As shown in Table 10, all of the largest absolute values of the mixed 2nd-order sensitivities involve the fission cross sections for the 12th energy group of isotopes 239Pu or 240Pu, and involve either the 2nd-order self-scattering cross sections in the 12th energy group for isotope 1H, or the 2nd-order self-scattering cross sections in the 7th energy group for isotopes 239Pu, 240Pu, 69Ga, 71Ga and C. As shown in Table 10, all of the largest elements in the respective sub-matrix are positive, and the vast majority of them are very small. The overall largest element in the matrix is .
Table 10.
Summary presentation of the matrix .
4.3.4. Results for the Relative Sensitivities
Table 11 presents the results for the 2nd-order mixed relative sensitivities , , of the leakage response with respect to the fission cross sections and the 3rd-order scattering cross sections for all isotopes. Most of the elements of are zero; the non-zero elements are very small, and the negative ones slightly outnumber the positive ones. For example, the -dimensional submatrix comprises 5288 negative elements and 4822 positive elements, while the remaining ones are zero. As shown in Table 11, the mixed 2nd-order sensitivities having the largest absolute values involve the fission cross sections for the 12th energy group of isotopes 239Pu or240Pu, and either the 3rd-order self-scattering cross sections for the 12th energy group for isotope 1H or the 3rd-order self-scattering cross sections for the 7th energy group for isotopes239Pu, 240Pu, 69Ga, 71Ga andC. The overall largest (in absolute value) element of the matrix is .
Table 11.
Summary presentation of the matrix .
The results in Table 9, Table 10 and Table 11 indicate that the largest mixed second-order relative sensitivities in matrices , and frequently involve the self-scattering cross sections in the 7th-energy group namely, , which is likely due to the fact that, for isotope 239Pu, the scattering cross section has the largest value among all scattering cross sections , for .
Figure 4 shows the energy-group structure of the fission spectrum for isotope 239Pu, highlighting that most of the spectrum is concentrated in the energy region , with the largest portion contained in group 12. It is therefore not surprising that most of the large mixed 2nd-order relative sensitivities of , , and are concentrated in the energy region of the fission cross sections of 239Pu. In particular, the 1st- and 2nd -order sensitivities of leakage response to the fission cross sections of 239Pu are both related to the 12th energy group, which is expected since energy-group 12 contains the largest portion of the fission spectrum of 239Pu.
Figure 4.
Histogram plot of fission spectrum for isotope 239Pu.
5. Computation of the 1st- and 2nd-Order Sensitivities of the PERP Leakage Response to the Average Number of Neutrons Per Fission
This Section reports the computational results for the 1st-order sensitivities and for the 2nd-order sensitivities . Section 6, Section 7 and Section 8 report the equations and results for , , , respectively.
5.1. First-Order Sensitivities
The expressions for computing the 1st-order sensitivities of the leakage response with respect to the parameters underlying the average number of neutrons per fission are derived using Equations (152), (156) and (157) in [5], as follows:
where the parameters correspond to the components of the vector as defined in Equation (A13) in Appendix A.
The multigroup adjoint fluxes in Equation (111) are the solutions of the 1st-Level Adjoint Sensitivity System (1st-LASS) as previously defined in Equations (7) and (8).
When the parameters correspond to the average number of neutrons per fission, i.e., , the following relation holds:
Inserting Equation (112) into Equation (111) yields the following simplified expression for computational purposes:
The numerical values of the 1st-order relative sensitivities, , of the leakage response with respect to the average number of neutrons per fission for the two fissionable isotopes contained in the PERP benchmark will be presented in Section 5.3, below, in tables that will also include comparisons with the numerical values of the corresponding 2nd-order unmixed relative sensitivities .
5.2. Second-Order Sensitivities
The equations needed for deriving the expression of the 2nd-order sensitivities are obtained by particularizing Equation (179) in [5] to the PERP benchmark, which takes the following particular form:
where the 2nd-level adjoint functions, and , are the solutions of the following 2nd-Level Adjoint Sensitivity System (2nd-LASS) presented in Equations (183)–(185) in [5]:
The parameters and in Equations (114), (115) and (117) correspond to the average number of neutrons per fission, and are therefore denoted as and , respectively. Noting that,
and inserting the results obtained in Equation (112) and Equations (119)–(122) into Equations (115), (117) and (114) reduces the latter equation to the following simplified expression:
where the 2nd-level adjoint functions, and are the solutions of the following simplified form of the 2nd-Level Adjoint Sensitivity System (2nd-LASS) obtained from Equations (115) and (117):
and subject to the boundary conditions shown in Equations (116) and (118), respectively.
5.3. Numerical Results for
The 2nd-order absolute sensitivities of the leakage response with respect to the parameters underlying the average number of neutrons per fission, i.e., for the fissionable isotopes and energy groups of the PERP benchmark are computed using Equation (123). The (Hessian) matrix of the 2nd-order absolute sensitivities has dimensions , since . The relative sensitivities corresponding to , which are denoted as and are defined as follows:
The numerical results obtained for the matrix have been partitioned into submatrices, each of dimensions , and the summary of the main features of each submatrix is presented in Table 12.
Table 12.
Summary presentation of the matrix .
The 2nd-order mixed sensitivities are all positive. Most of the elements are very small, but 52 elements have very large relative sensitivities, with values greater than 1.0, as summarized in Table 12. All of these 52 large sensitivities belong to the sub-matrix , and relate to the parameters corresponding to the average number of neutrons per fission in isotope 239Pu. The overall maximum relative sensitivity is . Additional details about the sub-matrix is provided in the following Section. Also noted in Table 12 is that all of the mixed 2nd-order relative sensitivities involving have absolute values smaller than 1.0. The elements with the maximum absolute value in each of the respective submatrices relate to the 12th energy group of for isotopes 239Pu and 240Pu.
5.3.1. Second-Order Unmixed Relative Sensitivities
The 2nd-order unmixed sensitivities , which are the elements on the diagonal of the matrix , can be directly compared to the values of the 1st-order relative sensitivities , for the leakage response with respect to the average number of neutrons per fission.
Table 13 presents the results obtained for the 1st- and 2nd-order unmixed relative sensitivities with respect to the average number of neutrons per fission for isotope 1 (239Pu). These results indicate that for energy groups , the values of the 2nd-order sensitivities are significantly larger than the corresponding values of the 1st-order sensitivities for the same energy group; for other energy groups, the 2nd-order relative sensitivities are smaller than the corresponding values of the 1st-order sensitivities. All of the 1st- and 2nd-order relative sensitivities are positive, and the largest values for the 1st-order and 2nd-order relative sensitivities are both related to the 12th energy group.
Table 13.
1st-order relative sensitivities and 2nd-order relative sensitivities for isotope 1 (239Pu).
Table 14 presents the 1st-order and 2nd-order unmixed relative sensitivities for isotope 2 (240Pu). The results in this table indicate that 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 one order of magnitude smaller than the corresponding values of the 1st-order ones for all energy groups. The largest 1st-order relative sensitivity is , and the largest 2nd-order unmixed relative sensitivity is , both occur for the 12th energy group of the average number of neutrons per fission for isotope 240Pu.
Table 14.
Comparison of 1st-order relative sensitivities and 2nd-order relative sensitivities for isotope 2 (240Pu).
5.3.2. Second-Order Relative Sensitivities
Table 15 presents the 2nd-order mixed relative sensitivity results obtained for , for the leakage response with respect to the parameters underlying the average number of neutrons per fission of isotope 239Pu. The majority of the larger 2nd-order relative sensitivities are concentrated in the energy region confined by the energy groups and . Shown in bold in Table 15 are the numerical values of 52 elements that have values greater than 1.0. The largest value among these sensitivities is attained by the relative 2nd-order unmixed sensitivity .
Table 15.
Components of having values greater than 1.0.
In addition to the sensitivities presented in Table 15, the following 2nd-order relative sensitivities in the matrix have values greater than 1.0: . Also, as shown in Table 15, the values of the mixed sensitivities in row are the largest among all rows. Likewise, the values of the mixed sensitivities in column are the largest among all groups .
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
This section presents the computation and analysis of the numerical results for the 2nd-order mixed sensitivities of the leakage response with respect to the average number of neutrons per fission and total microscopic cross sections of all isotopes of the PERP benchmark. Similarly, these mixed sensitivities can be computed using either the computation of or the computation of . These two distinct paths will be presented in Section 6.1 and Section 6.2, respectively.
6.1. Second-Order Sensitivities
The equations needed for deriving the expression of the 2nd-order sensitivities are obtained by particularizing Equation (177) in [5] to the PERP benchmark, which takes the following form:
The parameters and in Equation (127) correspond to the average number of neutrons per fission and total cross sections, and are therefore denoted as and , respectively.
Inserting the results obtained in Equation (50) into Equation (127), yields:
6.2. Alternative Path: Computing the Second-Order Sensitivities
The equations needed for deriving the expression for are obtained by particularizing Equation (160) in [5] to the PERP benchmark, which takes the following form:
where the adjoint functions and are the solutions of the 2nd-Level Adjoint Sensitivity System (2nd-LASS) presented in Equations (32), (34), (39) and (40) of Part I [1], which have been reproduced as Equations (57)–(60) in Section 3.2.
The parameters and in Equation (129) correspond to the total cross sections and the average number of neutrons per fission, respectively, and are therefore denoted as and . Inserting the results obtained in Equations (121) and (122) into Equation (129) yields:
where the flux moments and have been defined in Equations (43) and (44).
6.3. Numerical Results for
The second-order absolute sensitivities, , of the leakage response with respect to the average number of neutrons per fission and the total cross sections for all isotopes of the PERP benchmark have been computed using Equation (128), and have been independently verified by computing using Equation (130). Similarly, computing by using Equation (128) requires 120 PARTISN computations while computing using Equation (130) requires PARTISN computations. Thus, computing using Equation (128) is 3 times more efficient than computing using Equation (130).
The matrix has dimensions . The matrix of 2nd-order relative sensitivities corresponding to , denoted as , is defined as follows:
To facilitate the presentation and interpretation of the numerical results, the matrix has been partitioned into submatrices, each of dimensions . The main features of each of these submatrices is presented in Table 16.
Table 16.
Summary presentation of the matrix .
Most of the values of the elements in the matrix are very small, and the majority (10,780 out of 10,800) of these elements have negative values. The results in Table 16 indicate that, when the 2nd-order mixed relative sensitivities involve or the total cross sections of isotopes 240Pu, 69Ga and 71Ga, their absolute values are all smaller than 1.0, except for one element in the submatrix . The element with the most negative value in each of the submatrices is always related to for the 12th energy group and for either the 12th or the 30th energy group. There are 179 elements with large relative sensitivities, having absolute values greater than 1.0, as indicated in Table 16. Those large sensitivities reside in the submatrices , , and , respectively, and 178 out of the 179 large sensitivities involve the average number of neutrons per fission of isotope 239Pu, namely, , and the total cross sections of isotopes 239Pu, C and 1H. Of the sensitivities summarized in Table 16, the single largest relative value is .
6.3.1. Second-Order Relative Sensitivities
The submatrix comprises the 2nd-order mixed relative sensitivity results obtained for, , for the leakage response with respect to the average number of neutrons per fission of 239Pu and to the total microscopic cross sections of 239Pu. All elements in this submatrix have negative 2nd-order relative sensitivities. The largest 2nd-order mixed relative sensitivities are concentrated in the energy region confined by the energy groups and . The numerical values of these large elements are presented in Table 17, which indicates (in bold) the 72 elements that have values greater than 1.0. The largest absolute value in this submatrix is attained by the relative 2nd-order mixed sensitivity , involving the parameters representing the average number of neutrons per fission and total cross section of isotope 239Pu in the 12th energy group.
Table 17.
Components of having values greater than 1.0.
In addition to the sensitivities presented in Table 17, the following 2nd-order relative sensitivities in the matrix have absolute values greater than 1.0: , and . The absolute values of the mixed sensitivities in row are the largest among all rows, including rows not presented in Table 17. Similarly, the values of the mixed sensitivities in group are the most negative among all groups , except for the sensitivity value located in groups and , which is less negative than the value located in groups and .
6.3.2. Second-Order Relative Sensitivities
As presented in Table 18, the submatrix , comprising the 2nd-order relative sensitivities of the leakage response with respect to the average number of neutrons per fission of isotope 1 (239Pu) and the total cross sections of isotope 5 (C), includes 7 elements that have values greater than 1.0. All of these 7 large elements involve the total cross section for group of isotope 5 (C).
Table 18.
Components of having values greater than 1.0.
6.3.3. Second-Order Relative Sensitivities
The submatrix , comprises the 2nd-order relative sensitivities of the leakage response with respect to the average number of neutrons per fission of isotope 1 (239Pu) and the total microscopic cross sections of isotope 6 (1H). The submatrix includes 99 elements that have absolute values greater than 1.0, as specified (in bold) in Table 19 and Table 20. Of these 99 elements, 71 elements are located in the energy phase-space confined by the energy groups and , while the other 28 elements are located in energy groups or ; some of these sensitivities have very large negative values. The largest negative value is displayed by the 2nd-order relative sensitivity of the leakage response with respect to the 12th energy group of the parameter underlying the average number of neutrons per fission for 239Pu and the 30th energy group of the total cross section for 1H, namely, .
Table 19.
Elements of , having absolute values greater than 1.0.
Table 20.
Continuation of Table 19.
6.3.4. Second-Order Relative Sensitivities
The submatrix , comprising the 2nd-order sensitivities of the leakage response with respect to the average number of neutrons per fission of isotope 2 (240Pu) and the total cross sections of isotope 6 (1H), contains a single large element that has an absolute value greater than 1.0, namely, .
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
This Section presents the computation and analysis of the numerical results for the 2nd-order mixed sensitivities, , of the leakage response with respect to the average number of neutrons per fission and scattering microscopic cross sections of all isotopes of the PERP benchmark. The numerical values of the 2nd-order mixed sensitivities can alternatively be computed by using the symmetric expression . The path for computing the 2nd-order mixed sensitivities will be presented in Section 7.1. The path for computing the alternative expressions for will be presented in Section 7.2.
7.1. Computation of the Second-Order Sensitivities
Similar to the computation of as presented in Section 4.1, the equations needed for deriving the expressions of the 2nd-order sensitivities will differ from each other depending on whether the parameter corresponds to the 0th-order scattering cross sections or to the higher-order scattering cross sections. The two distinct cases are as follows:
- (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
The equations needed for deriving the expression of the 2nd-order mixed sensitivities are obtained by particularizing Equations (177) and (178) presented in [5] to the PERP benchmark, where Equation (178) provides the contributions arising directly from the parameters underlying the average number of neutrons per fission and scattering cross sections, while Equation (177) provides contributions arising indirectly through the total cross sections, since the 0th-order scattering cross sections are part of the total cross sections. The expression obtained by particularizing Equation (178) in [5] to the PERP benchmark yields:
In Equation (132), the parameters indexed by correspond to the average number of neutrons per fission, so that , while the parameters indexed by correspond to the 0th-order scattering cross sections, so that , respectively.
Inserting the results obtained in Equations (68) and (69) into Equation (132), using the addition theorem for spherical harmonics in one-dimensional geometry, performing the respective angular integrations, and setting in the resulting expression yields the following simplified form for Equation (132):
where the 0th-order moments , , and have been defined previously in Equations (15), (16), (27) and (28), respectively.
The contributions stemming from the specialized form of Equation (177) of [5], in conjunction with the relation , are as follows:
Inserting the result obtained in Equation (73) into Equation (134) yields the following simplified expression:
Collecting the partial contributions obtained in Equations (133) and (135), yields the following result:
7.1.2. Second-Order Sensitivities
When computing the 2nd-order sensitivities , the parameters correspond to the average number of neutrons per fission, while the parameters correspond to the th-order scattering cross sections, neither of which contribute to the total cross sections. Thus, the expression of is obtained by particularizing Equation (178) in [5] to the PERP benchmark, which yields,
Inserting the results obtained in Equations (68) and (69) into Equation (137), using the addition theorem for spherical harmonics in one-dimensional geometry and performing the respective angular integrations yields the following simplified form for Equation (137):
where the moments , , and have been defined in Equations (82), (83), (86) and (87), respectively.
7.2. Alternative Path: Computing the Second-Order Sensitivities
Due to the symmetry of the mixed 2nd-order sensitivities, the results computed using Equations (136) and (138) for can be verified by computing the expressions of the sensitivities , which also requires separate consideration of the zeroth-order scattering cross sections. The two cases involved are as follows:
- (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
The equations needed for deriving the expression of the 2nd-order mixed sensitivities are obtained by particularizing Equations (160) and (169) in [5] to the PERP benchmark. Particularizing Equation (169) in [5] to the PERP benchmark yields the following expression:
where the 2nd-level adjoint functions, and are the solutions of the 2nd-Level Adjoint Sensitivity System (2nd-LASS) presented in Equations (46), (48), (51) and (52) of Part II [2], which have been reproduced previously in Equations (89)–(92).
In Equation (139), the parameters indexed by correspond to the 0th-order scattering cross sections, so that , while the parameters indexed by correspond to the average number of neutrons per fission, so that . Inserting the results obtained in Equations (121) and (122) into Equation (139), yields the following simplified expression for Equation (139):
where the 0th-order moments and have been previously defined in Equations (94) and (95), respectively.
The contributions stemming from Equation (160) in [5] takes on the following particular form:
where the 2nd-level adjoint functions and are the solutions of the 2nd-Level Adjoint Sensitivity System (2nd-LASS) presented in Equations (30), (32), (36) and (37) of Part II [2], which were reproduced previously in Equations (97)–(100), respectively.
Inserting the results obtained in Equations (121) and (122) into Equation (141), yields the following simplified expression for Equation (141):
Collecting the partial contributions obtained in Equations (140) and (142), yields the following result:
7.2.2. Second-Order Sensitivities
For this case, the parameters correspond to the -order () scattering cross sections, denoted as , while the parameters correspond to the average number of neutrons per fission, denoted as , neither of them contribute to the total cross sections. Therefore, the expression of is obtained by particularizing Equation (169) in [5] to the PERP benchmark, which yields,
Inserting the results obtained in Equations (121) and (122) into Equation (144) yields the following expression:
7.3. Numerical Results for
The second-order absolute sensitivities, for the PERP benchmark, have been computed using Equations (136) and (138), and have been verified by computing using Equations (143) and (145). Similar to the computation of as shown in Section 4.3, computing the second-order sensitivities using Equations (136) and (138) requires a total of 120 forward and adjoint PARTISN computations to obtain all the adjoint functions to compute the 2nd-order sensitivities .
On the other hand, computing the alternative expression using Equations (143) and (145) would require 7101 forward and adjoint PARTISN computations to obtain the adjoint functions and . As has been explained in Section 4.3, the reason for needing “only” 7101, instead of , PARTISN computations is that all of the up-scattering and some of the down-scattering cross sections are zero for the PERP benchmark. Thus, computing using Equations (136) and (138) is about times more efficient than computing by using Equations (143) and (145).
The matrix has dimensions The matrix of 2nd-order relative sensitivities corresponding to , denoted as , is defined as follows:
To facilitate the presentation and interpretation of the numerical results, the matrix has been partitioned into submatrices, each of dimensions . The results for scattering orders , , , and , respectively, are summarized below, in Section 7.3.1, Section 7.3.2, Section 7.3.3 and Section 7.3.4.
7.3.1. Results for the Relative Sensitivities
Table 21 presents the results for 2nd-order relative sensitivities , of the leakage response with respect to the average number of neutrons per fission and the 0th-order scattering cross sections for all isotopes. All of these 2nd-order relative sensitivities are smaller than 1.0. For the 2nd-order mixed sensitivities , the values can be positive or negative, but there are more positive values than negative ones. For example, the submatrix , having dimensions , comprises 7601 positive elements, 2539 negative elements, while the remaining elements are zero. The largest absolute values of the mixed 2nd-order sensitivities in the submatrices all involve the 12th energy group of for isotopes 239Pu or 240Pu, and (mostly) the 0th-order self-scattering cross sections in the 12th energy group of isotopes239Pu, 240Pu, 69Ga, 71Ga andC, or (occasionally) the 0th-order out-scattering cross section of isotope 1H. All of the largest elements in the respective sub-matrix are positive, and the vast majority of them are very small. The overall largest element in the matrix is .
Table 21.
Summary presentation of the matrix .
7.3.2. Results for the Relative Sensitivities
Table 22 summarizes the results for 2nd-order mixed relative sensitivities of the leakage response with respect to the average number of neutrons per fission and the 1st-order scattering cross sections for all isotopes. Most of these 2nd-order mixed sensitivities are zero; the non-zero ones are mostly negative. For example, the submatrix , having dimensions , comprises 7918 elements with negative values, 2222 elements with positive values, while the remaining elements are zero. As shown in Table 22, the largest absolute values of the mixed 2nd-order sensitivities in the submatrices involve the 12th energy group of for isotopes 239Pu or 240Pu, and (mostly) the 1st-order self-scattering cross sections for the 12th energy group of isotopes239Pu, 240Pu, 69Ga, C and1H, or (occasionally) the 1st-order self-scattering cross sections for the 7th energy group of isotope 71Ga. All of the largest (in absolute value) elements are negative, and the vast majority of them are very small. The overall most negative value in the matrix is .
Table 22.
Summary presentation of the matrix .
7.3.3. Results for the Relative Sensitivities
Table 23 presents the results for 2nd-order mixed relative sensitivities , , of the leakage response with respect to the average number of neutrons per fission and the 2nd-order scattering cross sections for all isotopes. Most of the non-zero elements of are positive. For example, the submatrix , having dimensions , comprises 6439 positive elements, 3701 negative elements, while the remaining elements are zero. As shown in Table 23, all of the largest absolute values of the mixed 2nd-order sensitivities involve for the 12th energy group or the 7th energy group of isotopes 239Pu or240Pu, and (most of the time) involve either the 2nd-order self-scattering cross sections for the 7th energy group of isotopes 239Pu, 240Pu, 69Ga, 71Ga and C or (occasionally) the 2nd-order self-scattering cross sections for the 12th energy group of isotope1H. As shown in Table 23, all of the largest elements in the respective sub-matrix are positive, and the vast majority of them are very small. The overall largest element in the matrix is .
Table 23.
Summary presentation of the matrix .
7.3.4. Results for the Relative Sensitivities
Table 24 presents the results for 2nd-order mixed relative sensitivities , , of the leakage response with respect to the average number of neutrons per fission and the 3rd-order scattering cross sections for all isotopes. Most of the elements of are zero; the non-zero elements are very small, and the negative ones slightly outnumber the positive ones. For example, the -dimensional submatrix comprises 5375 negative elements, 4735 positive elements, while the remaining ones are zero. As shown in Table 24, the mixed 2nd-order sensitivities having the largest absolute values involve for the 12th energy group or (occasionally) the 7th energy group of isotopes 239Pu or240Pu, and the 3rd-order self-scattering cross sections for the 7th energy group of isotopes239Pu, 240Pu, 69Ga, 71Ga and C, or (occasionally) the 3rd-order self-scattering cross sections for the 12th energy group of isotope 1H. The overall largest (in absolute value) element of the matrix is .
Table 24.
Summary presentation of the matrix .
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
This Section presents the computation and analysis of the numerical results for the 2nd-order mixed sensitivities of the leakage response with respect to the average number of neutrons per fission and fission microscopic cross sections of all isotopes of the PERP benchmark. Likewise, the numerical values of the 2nd-order mixed sensitivities can also be computed by using the alternative expression for . The formulas for computing the 2nd-order mixed sensitivities are presented in Section 8.1, while the formulas for computing, alternatively, the expressions for are presented in Section 8.2.
8.1. Computing the Second-Order Sensitivities
The equations needed for deriving the expression of the 2nd-order sensitivities are obtained by particularizing Equations (177) and (179) in [5] to the PERP benchmark and adding their respective contributions. The expression obtained by particularizing Equation (179) in [5] takes on the following form:
The parameters and in Equation (147) correspond to the average number of neutrons per fission and fission cross sections, and are therefore denoted as and , respectively. Noting that
and inserting the results obtained in Equations (148), (23) and (24) into Equation (147), yields the following simplified expression for Equation (147):
The contributions stemming from Equation (177) in [5], in conjunction with the relations , take on the following particular form:
Inserting the results obtained in Equation (37) into Equation (150), yields the following simplified expression for Equation (150):
Collecting the partial contributions obtained in Equations (149) and(151), yields the following final expression:
8.2. Alternative Path: Computing the Second-Order Sensitivities
The equations needed for deriving the expression of the 2nd-order sensitivities are obtained by particularizing Equations (160) and (179) in [5] to the PERP benchmark. The expression obtained by particularizing Equation (179) in [5] to the PERP benchmark, takes on the following form:
In Equation (153), the 2nd-level adjoint functions , and , are the solutions of the 2nd-Level Adjoint Sensitivity System (2nd-LASS) presented in Equations (18)–(21) in Section 2.2.
The parameters and in Equation (153) correspond to the fission cross sections and the average number of neutrons per fission, and are therefore denoted as and , respectively. Noting that,
and inserting the results obtained in Equations (120), (121) and (154) into Equation (153), yields the following simplified expression for Equation (153):
The contributions stemming from Equation (160) in [5], in conjunction with the relations , yield the following particular form for these contributions:
where the 2nd-level adjoint functions , and , are the solutions of the 2nd-Level Adjoint Sensitivity System (2nd-LASS) presented in Equations (33), (35), (39) and (40) in Section 2.2.
Inserting the results obtained in Equations (120) and (121) into Equation (156) and performing the respective angular integrations yields the following simplified expression for Equation (156):
Collecting the partial contributions obtained in Equations (155) and (157), yields the following final expression:
8.3. Numerical Results for
The second-order absolute sensitivities, , of the leakage response with respect to the average number of neutrons per fission and fission cross sections for all isotopes of the PERP benchmark have been computed using Equation (152), and have been independently verified by computing using Equation (158). For this case, computing using Equation (152) is as efficient as computing using Equation (158) since either path requires 120 forward and adjoint PARTISN computations to obtain all the needed 2nd-level adjoint functions.
The matrix of 2nd-order absolute sensitivities has dimensions , since . For convenient comparisons, the numerical results presented in this section are presented in unit-less values of the relative sensitivities that correspond to , which are denoted as and are defined as follows:
The numerical results obtained for the matrix have been partitioned into submatrices, each of dimensions . The summary of the main features of each submatrix is presented in Table 25.
Table 25.
Summary presentation of the matrix .
The 2nd-order mixed sensitivities are mostly positive. Among the elements in the matrix , 3557 out of 3600 elements have positive values, and most of them are very small; however, 28 out of these 3600 elements have large relative sensitivities, with values greater than 1.0, as noted inTable 25. All of these larger sensitivities reside in the sub-matrix , and relate to the fission parameters for isotope 239Pu. The overall maximum relative sensitivity is Additional details about the sub-matrix are provided in the following section. The results in Table 25 also indicate that all of the mixed 2nd-order relative sensitivities involving the fission parameters (either or ) of isotope 240Pu have absolute values smaller than 1.0. Moreover, as shown in this table, the elements with the maximum absolute value in each of the respective submatrices all involve the fission parameters for the 12th energy group (i.e., or ) of isotopes 239Pu and 240Pu.
The numerical results for the elements of the submatrix , , of 2nd-order mixed relative sensitivities of the leakage response with respect to the average number of neutrons per fission and fission cross sections of isotope 239Pu, indicate that the majority (899 out of 900) of the elements of this submatrix have positive 2nd-order relative sensitivities; only 1 element is negative. Table 26 presents the 28 elements (in bold) of which have values greater than 1.0. The largest value among these sensitivities is attained by the relative 2nd-order mixed sensitivity .
Table 26.
Components of having values greater than 1.0.
9. Quantification of Uncertainties in the PERP Leakage Response Due to Uncertainties in Fission Cross Sections
Correlations between the group-averaged microscopic fission cross sections or correlations between these cross sections and other cross sections are not available for the PERP benchmark. When such correlations are unavailable, the maximum entropy principle (see, e.g., [9]) indicates that neglecting them minimizes the inadvertent introduction of spurious information into the computations of the various moments of the response’s distribution in parameter space. The formulas for computing the expected value, variance and skewness of the response distribution by taking into account the 2nd-order response sensitivities together with the standard deviations of the group-averaged fission microscopic cross sections parameter correlations are as follows:
1. The expected value, , of the leakage response has the following expression:
where the subscript “f” indicates contributions solely from the group-averaged uncorrelated fission microscopic cross sections, and where the term , which provides the 2nd-order contributions, is given by the following expression:
In Equation (161), the quantity denotes the standard deviation associated with the imprecisely known model parameter .
2. Taking into account contributions solely from the group-averaged uncorrelated and normally-distributed microscopic fission cross sections (which will be indicated by using the superscript “(U,N)” in the following equations), the expression for computing the variance, denoted as , of the PERP leakage response has the following form:
where the first-order contribution term, , to the variance is defined as
while the second-order contribution term, , to the variance is defined as
3. Taking into account contributions solely from the group-averaged uncorrelated normally-distributed fission microscopic cross sections, the third-order moment, , of the leakage response for the PERP benchmark takes on the following form:
As Equation (165) indicates, if the 2nd-order sensitivities were unavailable, the third moment would vanish and the response distribution would by default be assumed to be Gaussian.
4. The skewness, , due to the variances of microscopic fission cross sections in the leakage response, , is defined as follows:
The effects of the first- and, respectively, second-order sensitivities on the response’s expected value, variance and skewness can be quantified by considering typical values for the standard deviations for the uncorrelated group-averaged isotopic fission cross sections, using these values together with the respective sensitivities computed in Section 2 in Equations (161)–(166). The results thus obtained are presented in Table 27, considering uniform parameter standard deviations of 1%, 5%, and 10%, respectively. These results indicate that the effects of both the 1st- and 2nd-order sensitivities on the expected response value, standard deviation and skewness are small, which is not surprising in view of the small values for the 1st- and 2nd-order sensitivities already presented in Table 2 and Table 3.
Table 27.
Comparison of Response Moments Induced by Various Relative Standard Deviations Assumed for the Parameters .
The relative effects of uncertainties in the fission cross sections can be compared to the corresponding effects stemming from the total and, respectively, scattering cross sections, by considering standard deviations of 10% for all of these cross sections and by comparing the corresponding results shown in Table 27 with the corresponding results presented in Table 25 of Part I [1] and Table 19 of Part II [2]. This comparison reveals that the following relations hold:
The above relations indicate that the contributions to the leakage response moments stemming from the group-averaged uncorrelated microscopic fission cross sections are much smaller than the corresponding contributions stemming from the group-averaged uncorrelated microscopic total cross sections but are much greater than the corresponding contributions stemming from the group-averaged uncorrelated microscopic scattering cross sections.
It is important to note that the results presented in Table 27 consider only the standard deviations of the group-averaged microscopic fission cross sections, since correlations between these parameters are unavailable. On the other hand, the results presented in Section 3 indicated that the largest values are displayed by several mixed 2nd-order sensitivities of the leakage response with respect to the total and fission cross sections, which are by several times larger than the values of the unmixed sensitivities. Recall that the following sensitivities have absolute values larger than 1.0: (a) 11 elements of the matrix , , presented in Table 4, in which only one of them is included in the above computations; (b) 35 elements of the matrix , , presented in Table 5; (c) 1 elements of the matrix as listed in Table 5; (d) 48 elements of the matrix , presented in Table 5. However, the effects of these sensitivities on the uncertainties in the response distribution can be taken into account only if the corresponding correlations among the various model parameters were available.
10. Uncertainties in the PERP Leakage Response Stemming from Uncertainties in the Average Number of Neutrons per Fission
The correlations between the average number of neutrons per fission are unknown, so these parameters will be assumed to be uncorrelated, since this assumption is the least biased, according to the maximum entropy principle [9] in avoiding the introduction of spurious information in the uncertainty quantification computations. Similar to those formulas presented in Section 9, upto 2nd-order response sensitivities, the expected value, , of the leakage response has the following expression:
where the subscript “” and superscript “U” indicate contributions solely from the group-averaged uncorrelated parameters underlying the average number of neutrons per fission, and where the term , which provides the 2nd-order contributions, is given by the following expression:
In Equation (168), the quantity denotes the standard deviation associated with the imprecisely known model parameter .
Considering contributions solely from the group-averaged uncorrelated parameters underlying the average number of neutrons per fission, the expression for computing the variance, denoted as , of the PERP leakage response has the following form:
In Equation (169), the term denotes the first-order contributions to the variance and is defined as follows:
while the second-order contribution term, to the variance is defined as follows:
Again, taking into account contributions solely from the group-averaged uncorrelated parameters underlying the average number of neutrons per fission, the third-order moment, , of the leakage response for the PERP benchmark takes on the following form:
As Equation (172) indicates, if the 2nd-order sensitivities were unavailable, the third moment would vanish and the response distribution would need, by default, to be assumed to be Gaussian. The skewness, , of the leakage response, , which indicates the degree of the distribution’s asymmetry with respect to its mean, due to the variances of the average number of neutrons per fission, is defined as follows:
Table 28 shows the results computed using Equations (167)–(173) together with the 1st- and 2nd-order respective sensitivity values presented in Section 5.3, for uniform parameter standard deviations of 1%, 5%, and 10% of , respectively.
Table 28.
Comparison of Response Moments Induced by Various Relative Standard Deviations Assumed for the Parameters .
The relative effects on the leakage response of uncertainties in the average number of neutrons per fission can be compared to the corresponding effects stemming from the fission and total cross sections. A final comparison, with corresponding conclusions, will be made after all of the 2nd-order sensitivities of the PERP leakage response to the PERP benchmark’s underlying nuclear data are obtained. Thus, comparing the results shown in Table 28 for standard deviations of 10% with the corresponding results presented in Table 27 for the fission cross sections and Table 25 of Part I [1] for the total cross sections reveals that:
The above comparisons indicate that the contributions to the leakage response moments stemming from the group-averaged uncorrelated parameters underlying the average number of neutrons per fission are much smaller than the corresponding contributions stemming from the group-averaged uncorrelated microscopic total cross sections but are bigger than the corresponding contributions stemming from the group-averaged uncorrelated microscopic fission cross sections. Again, it is important to note that the results presented in Table 28 consider only the standard deviations of the uncorrelated parameters underlying the average number of neutrons per fission, since correlations between these parameters are unavailable. On the other hand, the results presented in Section 5, Section 6 and Section 7 indicated that the largest values are displayed by several mixed 2nd-order sensitivities of the leakage response with respect to and , and with respect to and , which are much larger than the values of the unmixed sensitivities. Recall that the following sensitivities have absolute values larger than 1.0: (a) 52 elements of the matrix , as summarized in Table 15; only 6 of these are included in the computations leading to the results shown in Table 28; (b) 72 elements of the matrix , , presented in Table 17; (c) 7 elements of the matrix as listed in Table 18; (d) 99 elements of the matrix presented in Table 19 and Table 20; (e) 1 element of the matrix presented in Section 6.3.4; and (f) 28 elements of the matrix presented in Table 26. However, the effect of these large sensitivities on the uncertainties in the response distribution cannot be considered presently because the corresponding correlations among the various model parameters are not available.
11. Conclusions
This work has presented results for the first-order sensitivities, , and the second-order sensitivities of the PERP total leakage response with respect to the group-averaged microscopic fission cross sections, and the mixed second-order sensitivities and of the leakage response with respect to the group-averaged microscopic fission/total cross sections and corresponding fission and scattering cross sections. In addition, this work has also presented results for and , i.e., the first- and, respectively, second-order sensitivities of the PERP total leakage response with respect to the parameters underlying the benchmark’s average number of neutrons per fission, as well as results for the mixed second-order sensitivities for , , and .
For the sensitivities with respect to the fission cross sections, the following conclusions can be drawn from the results reported in this work:
- 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.
For the sensitivities with respect to the parameters underlying the average number of neutrons per fission, the following conclusions can be drawn from the results reported in this work:
- 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.
Subsequent works [10,11] will report the values and effects of the 1st-order and 2nd-order sensitivities of the PERP’s leakage response with respect to the group-averaged source parameters, fission spectrum, and isotopic number densities, along with the overall conclusions and implications of this pioneering and uniquely comprehensive 2nd-order sensitivity analysis and uncertainty quantification of the PERP reactor physics benchmark.
Author Contributions
D.G.C. conceived and directed the research reported herein, developed the general theory 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, and the uncertainty equations for response moments. R.F. derived the expressions of the various derivatives with respect to the model parameters to the PERP benchmark and performed all the numerical calculations. J.A.F. has provided initial guidance to R.F. for using PARTSN and SOURCES4C, and has independently verified, using approximate finite-difference computations with selected perturbed parameters, several numerical results obtained by R.F., M.C.B. and F.D.R. contributed programing of equations underlying the uncertainty analysis formalism.
Acknowledgments
This work was partially funded by the United States National Nuclear Security Administration’s Office of Defense Nuclear Nonproliferation Research and Development, grant unmber 155040-FD50.
Conflicts of Interest
The authors declare no conflict of interest. The founding sponsors had no role in the design of the study; in the collection, analyses, or interpretation of data; in the writing of the manuscript, and in the decision to publish the results.
Appendix A. Definitions of PERP Model Parameters
As presented in Part I [1], the components of the vector of 1st-order sensitivities of the leakage response with respect to the model parameters, denoted as , was defined as follows:
The symmetric matrix of 2nd-order sensitivities of the leakage response with respect to the model parameters, denoted as , was defined as follows:
As defined in Equation (1), the vector denotes the “vector of imprecisely known model parameters”, with vector-components , , , , , and , comprising the various model parameters for the microscopic total cross sections, scattering cross sections, fission cross sections, average number of neutrons per fission, fission spectra, sources, and isotopic number densities, which have been described in Part I [1]. For easy referencing, the definitions of these model parameters will be recalled in the remainder of this Appendix.
The total cross section for energy group is computed for the PERP benchmark using the following expression:
where denotes the materials in the PERP benchmark; and denote, respectively, the tabulated group microscopic fission and neutron capture cross sections for group Other nuclear reactions are negligible in the PERP benchmark. As discussed in Part I [1], the total cross section will depend on the vector of parameters , which is defined as follows:
where
In Equations (A4)–(A6), the dagger denotes “transposition,” denotes the microscopic total cross section for isotope and energy group , denotes the respective isotopic number density, and denotes the total number of isotopic number densities in the model. Thus, the vector comprises a total of imprecisely known “model parameters” as its components.
The scattering transfer cross section from energy group into energy group is computed using the finite Legendre polynomial expansion of order :
where denotes the -th order Legendre-expanded microscopic scattering cross section from energy group into energy group for isotope . In view of Equation (A7), the scattering cross section depends on the vector of parameters , which is defined as follows:
The expressions in Equations (A7) and (A3) indicate that the zeroth order (i.e., ) scattering cross sections must be considered separately from the higher order (i.e., ) scattering cross sections, since the former contribute to the total cross sections, while the latter do not. Therefore, the total number of zeroth-order scattering cross section comprise in is denoted as , where ; and the total number of higher order (i.e., ) scattering cross sections comprised in is denoted as , where , with . Thus, the vector comprises a total of imprecisely known components (“model parameters”).
The transport code PARTISN [4] computes the quantity using directly the quantities , which are provided in data files for each isotope , and energy group , as follows
In view of Equation (A10), the quantity depends on the vector of parameters , which is defined as follows:
where
and where denotes the microscopic fission cross section for isotope and energy group , denotes the average number of neutrons per fission for isotope and energy group , and denotes the total number of fissionable isotopes. For the purposes of sensitivity analysis, the quantity , can be obtained by using the relation , where the isotopic fission cross sections are available in data files for computing reaction rates.
The quantity in Equation (3) quantifies the material fission spectrum in energy group , and is defined in PARTISN [4] as follows:
where the quantity denotes the isotopic fission spectrum in energy group , while the quantity denotes the corresponding spectrum weighting function.
Appendix B
The sensitivities presented in this work have been computed by specializing the general expressions derived by Cacuci [5] to the PERP benchmark. For easy reference, the equations from Ref. [5] used in this work are reproduced in the following:
Equation (149) in [5]:
Equation (150) in [5]:
Equation (152) in [5]:
Equations (156) and (157) in [5]:
Equation (158) in [5]:
Equation (159) in [5]:
Equation (160) in [5]:
Equations (164)–(166) in [5]:
Equation (167) in [5]:
Equation (169) in [5]:
Equations (173) through (175) in [5]:
Equation (177) in [5]:
Equation (178) in [5]:
Equation (179) in [5]:
Equations (183)–(185) in [5]:
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 | |
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