Introduction
Uncertainty analysis is currently required in nuclear engineering research. As a major contributor to the energy released after a reactor shutdown, the decay heat of fission products is crucial in various aspects of nuclear engineering, such as reactor design, nuclear power plant safety analysis, and nuclear fuel waste management [1-3]. Significant effort has been devoted to the accurate estimation and uncertainty analysis of decay heat, which is typically performed within the framework of the summation method [4-8].
The summation calculations of the decay heat are dependent on the decay and fission yield data, which have been evaluated and compiled in sublibraries by nuclear data libraries such as ENDF/B [9], JENDL [10] and JEFF [11]. However, these libraries contained only the best estimates and uncertainties without covariances for the fission yield and branching ratio. In particular, the covariances of fission yields play an important role in the uncertainty analysis of fission products and can significantly reduce the impact of fission yield on the total uncertainty of the system [12-15].
Several efforts have been made to obtain fission yields using complete covariance matrices. A relatively simple procedure was provided by Katakura [4, 12], in which the chain yields were regarded as approximate mass distributions of independent fission yields and were used as a single constraint. The covariances given by this method exist only between fission products with the same mass number. Furthermore, constraints from experimental data and physical models were applied to generate optimized fission yield data and correlations between all isotopes [15-20]. Recently, different types of neural networks have been adopted to estimate fission yields and their uncertainties [21-26], in which complicated data relationships and the propagation of high-order errors can be handled naturally. At present, an international effort coordinated by IAEA is ongoing with the aim of updating and improving the fission yield of actinide nuclides [27].
In this study, we focused on the generation of fission yield covariances in which the constraints from the chain yield data and the physical conservation equation were considered. Covariance matrices are generated using the generalized least square (GLS) updating approach [28] and a slight adjustment is made to the fission yield data simultaneously. Fission pulse decay heat (FPDH) calculations were performed for thermal neutron-induced fission of 235U, which is denoted by 235U(nth, f). The original data from ENDF/B-VIII.0, JENDL-5, and JEFF-3.3 [9-11] and the corresponding updated data were used. Uncertainty analysis was performed using the generalized perturbation theory [29, 30], including the uncertainties propagated from the fission yield and decay data.
The remainder of this paper is organized as follows. Theoretical methodologies for covariance generation, summation calculation, and generalized perturbation theory are described in Sect. 2. The calculated results and a discussion of the decay heat and its uncertainties are presented in Sect. 3. Finally, the conclusions are presented in Sect. 4.
Methodology
Independent fission yield data and covariance generation
The independent fission yield (IFY) YI(A, Z, M is required in decay heat calculations, which represents the probability of a particular nucleus with mass A, charge Z and isomeric state M being produced directly from one fission after the emission of prompt neutrons and photons but before the emission of delayed neutrons. The most commonly used general-purpose nuclear data libraries: ENDF/B, JENDL and JEFF, provide IFY data with uncertainties as standard deviations. ENDF/B-VIII.0 takes binary fission only, whereas JENDL-5 and JEFF-3.3 both include the light products of ternary fission. To date, no correlation between the fission yield has been reported in these libraries.
The IFY data in these libraries are generally provided by empirical models that are constrained by physical conditions and conservation equations, reflecting the general nature of a fissioning system. These properties should hold in the covariance generation for IFYs, corresponding to the constraint conditions in the GLS updating process. In the present work, the following constraints are employed:
(1) Mass and charge conservation
In a real fission event, the compound nucleus (CN) is generally split into two fission fragments in a process called binary fission. These fragments decay into fission products (FPs) by releasing neutrons and photons. Furthermore, ternary fission may occur with a low probability (~0.2–0.5%), producing extra light-charged particles (LCP), such as protons, triton and α particles [31]. Notably, light-charged particles were also included in the fission products in this study, and the yield data of LCPs and relatively heavy fission products would be updated together within the GLS updating process.
Conservation laws state that the mass and charge numbers of the compound nucleus must be conserved as follows:_2026_06/1001-8042-2026-06-101/alternativeImage/1001-8042-2026-06-101-M001.png)
_2026_06/1001-8042-2026-06-101/alternativeImage/1001-8042-2026-06-101-M002.png)
(2) Normalization of IFYs
The sum of IFYs for FPs except LCPs should be 2 by definition, that is,._2026_06/1001-8042-2026-06-101/alternativeImage/1001-8042-2026-06-101-M003.png)
(3) Normalization of heavier mass yields:
For a set of IFY data, there should be a midpoint mass number Amid such that the yields of FPs on either side of this midpoint are equal to one when the yield data of LCPs are not counted. As there is a normalization constraint of IFYs to be 2, this condition can be expressed without repetition as_2026_06/1001-8042-2026-06-101/alternativeImage/1001-8042-2026-06-101-M004.png)
(4) Charge symmetry
In low-energy neutron-induced fission, FP has a low probability of releasing charged particles during its prompt de-excitation. Therefore, the charge distribution of IFYs should be strictly symmetrical if only binary fission occurs, whereas this symmetry is slightly broken by ternary fission. Following the procedure of Mills [32], the charge symmetry condition was applied to the charge number pairs (Z,ZCN-Z) with relatively large yields:_2026_06/1001-8042-2026-06-101/alternativeImage/1001-8042-2026-06-101-M005.png)
_2026_06/1001-8042-2026-06-101/alternativeImage/1001-8042-2026-06-101-M006.png)
(5) Chain yield constraints:
The chain yield (ChFY), YCh(A, is defined as the sum of the cumulative yields of the last stable nuclei with the same mass number A and is much more precise than IFY experimental data. A strong negative correlation between different nuclides occurs if ChFY is used as a constraint in the evaluation of IFY.
As noted by England and Rider [33], the chain yields were evaluated after both prompt and delayed neutron emissions. Therefore, the pre-delayed neutron mass yields of IFYs must be corrected to post-delayed neutron chain yields. Based on this definition, ChFY can be calculated as follows:_2026_06/1001-8042-2026-06-101/alternativeImage/1001-8042-2026-06-101-M007.png)
Currently, there are thousands of radionuclides in the evaluated nuclear data libraries, and their half-lives T1/2 vary from ~10-20 to 1020. However, not all radionuclides should be considered in ChFY calculations. The chain yields are close to the mass distribution of the independent fission yields
Figure 1 shows the calculated ChFYs for the thermal neutron-induced fission of 235U using the fission yield and decay data in ENDF/B-VIII.0. When Tcut=0, all decay processes were eliminated in ChFY calculations, and the result was equivalent to the mass distribution of the independent fission yields. With increasing Tcut, the calculated YCh(A) departs from YI(A gradually and converges at Tcut=1 min. The relative divergence between the converged YCh(A and YI(A can reach ~10%, mainly located in the mass regions A=83–97 and 135–140. These differences were primarily attributed to the crossing mass-chain decay processes of radionuclides with half-lives between 1 ms and 1 min. The decay processes of nuclides with T1/2>1 min hardly changed in the chain yields. Hence, Tcut=1 min is adopted in the following calculations: This cutoff is consistent with the evaluation of England and Rider [33], in which the half-lives of the involved delayed neutron precursors were no longer than 1 min.
_2026_06/1001-8042-2026-06-101/alternativeImage/1001-8042-2026-06-101-F001.jpg)
The generalized least squares method [16, 28] was adopted to estimate the covariance matrices of IFYs. For a certain fissioning system, the independent fission yields in the evaluated library are regarded as prior knowledge of the parameters θa=YI, along with a diagonal prior covariance matrix Va whose diagonal elements are taken from the corresponding variances. The constraints above can be summarized as the observation equation η~ya=St·θa, where η is a vector and S denotes the design matrix, In the GLS approach, the prior parameters and covariance can be updated asfollows:_2026_06/1001-8042-2026-06-101/alternativeImage/1001-8042-2026-06-101-M008.png)
In this study, V is also a diagonal matrix with diagonal elements obtained from the variances of η. The uncertainties of
Table 1 lists the impact of GLS updating process on each constraint for the thermal neutron-induced fission of 235U. The residual errors x=η–St·θ and their uncertainties
| 235U(nth,f) | ENDF/B-VIII.0 | JENDL-5 | JEFF-3.3 | |||
|---|---|---|---|---|---|---|
| ORI | UPD | ORI | UPD | ORI | UPD | |
| |
-1.42×-2 ± 3.79 | 3.20×-3 ± 7.48×10-3 | -6.40×-3 ± 3.01 | -3.00×-3 ± 6.13×10-3 | 1.00×-2 ± 4.18 | 3.20×-3 ± 1.14×10-2 |
| |
-5.31×-2 ± 1.51 | 0 ± 9.97×-5 | -5.45×-2 ± 1.18 | 0 ± 1.00×-4 | 1.60×-4 ± 1.64 | 0 ± 1.00×-4 |
| |
0 ± 3.46×-2 | 0 ± 9.85×-7 | 0 ± 2.55×-2 | 0 ± 1.00×-6 | 0 ± 3.52×-2 | 0 ± 9.94×-7 |
| |
-7.40×-5 ± 1.72×10-2 | 6.05×-5 ± 9.55×10-5 | 1.32×-4 ± 1.76×10-2 | 4.84×-5 ± 9.41×10-5 | 0 ± 2.48×-2 | 0 ± 9.85×-5 |
| χ2 for charge symmetry | 2.23 | 1.50 | 10.36 | 0.80 | 0 | 0.01 |
| χ2 for chain yield | 8.48 | 3.23 | 9.09 | 2.52 | 9.78 | 0.03 |
For the charge symmetry and chain yield constraints, the quantity χ2 was adopted to quantitatively assess the improvement, which is defined as_2026_06/1001-8042-2026-06-101/alternativeImage/1001-8042-2026-06-101-M009.png)
_2026_06/1001-8042-2026-06-101/alternativeImage/1001-8042-2026-06-101-F002.jpg)
_2026_06/1001-8042-2026-06-101/alternativeImage/1001-8042-2026-06-101-F003.jpg)
As shown in Eq. (8), GLS updating procedure not only generates the correlation of fission yields but also adjusts the yield data. A comparison of the original IFYs in ENDF/B-VIII.0 with updated IFYs are presented in Fig. 4 for thermal neutron-induced fission of 235U. The adjustments are visible only when IFYs have high sensitivity to the constraint system. Strong reductions occur in the variances as they are removed from the diagonal part and reintroduced as correlations between IFYs.
_2026_06/1001-8042-2026-06-101/alternativeImage/1001-8042-2026-06-101-F004.jpg)
Figure 5 presents the correlation matrices for YI(A and YI(Z) of the updated IFYs based on the data file from ENDF/B-VIII.0. The correlation matrix _2026_06/1001-8042-2026-06-101/alternativeImage/1001-8042-2026-06-101-M010.png)
_2026_06/1001-8042-2026-06-101/alternativeImage/1001-8042-2026-06-101-F005.jpg)
Summation calculation and generalized perturbation theory
The fission pulse decay heat is the heat generated by radioactive decay after an instantaneous burst of fission occurring at time t=0. FPDH can be calculated using the summation method asfollows:_2026_06/1001-8042-2026-06-101/alternativeImage/1001-8042-2026-06-101-M011.png)
The time evolution of N(t) follows the Bateman’s equation [36]:_2026_06/1001-8042-2026-06-101/alternativeImage/1001-8042-2026-06-101-M012.png)
The uncertainty of FPDH was carried out with generalized perturbation theory [29, 30]. The variance of the decay heat VH can be calculated using the sandwich formula asfollows:_2026_06/1001-8042-2026-06-101/alternativeImage/1001-8042-2026-06-101-M013.png)
_2026_06/1001-8042-2026-06-101/alternativeImage/1001-8042-2026-06-101-M014.png)
Vσ is the covariance matrix of nuclear data. The covariance of the fission yield was generated in Sect. 2.1. Vσ of the branching ratio is meaningful for the different decay pathways of a single nuclide because of the normalization condition _2026_06/1001-8042-2026-06-101/alternativeImage/1001-8042-2026-06-101-M015.png)
Results and discussions
For each evaluated nuclear data library, two sets of data were used for FPDH calculations.
Set A: Original fission yield data with decay data.
Set B: GLS updates fission yield data with decay data.
No adjustments were made to the decay data in this study.
FPDH results
The light particles and electromagnetic components of FPDH for thermal neutron-induced fission of 235U are presented in Figs. 6 and 7 respectively, which were calculated with Set-A and Set-B from ENDF/B-VIII.0, JENDL-5, JEFF-3.3. The experimental data were obtained from the IAEA CoNDERC database [38]. The resulting decay heat curves are in good agreement at cooling times above 1000 s, except that JEFF-3.3 provides a relatively large electromagnetic decay heat during 104–105 s. The discrepancies between the calculated results mainly occur within 1000 s and become significant at cooling times shorter than 1 s. In general, all the calculated results at cooling times below 1000 s are within the error range of the experimental data, except for the underestimation of the electromagnetic decay heat for JEFF-3.3 from 5 to 50 s.
_2026_06/1001-8042-2026-06-101/alternativeImage/1001-8042-2026-06-101-F006.jpg)
For both light particles and electromagnetic decay heats, the updated IFYs lead to an enhancement of up to ~5% at cooling times shorter than 1 s and increase the peaks of the curves by approximately 1–2% for ENDF/B-VIII.0 and JENDL-5, whereas the divergences between the calculated results with Set-A and Set-B are small for JEFF-3.3. These differences reveal that the update on IFYs themselves is moderate for ENDF/B-VIII.0 and JENDL-5 but negligible for JEFF-3.3.
Uncertainties of FPDH
The uncertainties in FPDH were propagated from those of the fission yield, decay energy, decay constant, and branching ratio, as formulated in Sect. 2.2. Computations were carried out with both Set-A and Set-B. To perform an uncertainty analysis with the Set-A data, a diagonal covariance matrix is given for the fission yield data, in which the diagonal elements are taken from their variances.
Figures 8 and 9 show the relative uncertainties of the light particles and electromagnetic decay heat for 235U(nth,f), including the contributions of each type of nuclear data. The uncorrelated yield data in Set-A provided a ~4% uncertainty in all cases, dominating the total uncertainty for cooling times longer than 100 s. In contrast, the contribution from the yield data is strongly reduced in Set B, and decreases gradually as time evolves, which is a result of the generated covariance matrix.
_2026_06/1001-8042-2026-06-101/alternativeImage/1001-8042-2026-06-101-F008.jpg)
_2026_06/1001-8042-2026-06-101/alternativeImage/1001-8042-2026-06-101-F009.jpg)
The uncertainties propagated from the decay energy, decay constant, and branching ratio are almost unchanged in the Set-A and Set-B results because the decay data have not been adjusted. In general, the decay energy was the primary contributor among the three types of decay data. Notably, the decay energy uncertainty obtained with JENDL-5 is much smaller than those obtained with ENDF/B-VIII.0 and JEFF-3.3 at cooling times shorter than 100 s. This is largely because JENDL-5 provides decay energy uncertainties for more radionuclides than ENDF/B-VIII.0 and JEFF-3.3. These radionuclides are primarily short-lived and release energy during early cooling. Therefore, the assumed 100% uncertainties were adopted less for JENDL-5 decay energy data, resulting in a smaller uncertainty.
With the generated covariance of the yield data, the uncertainties of the light particles and electromagnetic decay heat at cooling time 0.1 s are approximately 10% for ENDF/B-VIII.0 and JEFF-3.3, 5% for JENDL-5. For cooling times longer than 105 s, the uncertainties decreased to approximately 1% for all three libraries. The main component of the uncertainty for the light particle decay heat is the decay energy uncertainty. This situation indicates that the electromagnetic decay heat uncertainty obtained with ENDF/B-VIII.0 and JEFF-3.3, while the uncertainties of yield data and decay energy dominate the total uncertainty of electromagnetic heat at cooling times shorter and longer than 50 s, respectively, for JENDL-5.
Contributions of important fission products and their sensitive coefficients
Because GLS updating procedure generates covariance and adjusts IFYs simultaneously, we are concerned about its influence on the contributions of important fission products to decay heat, as well as their sensitivity coefficients. The analysis was performed at a cooling time of 10 s, which is the position of the curve peak for the light-particle heat, as shown in Fig. 6. Moreover, an underestimation was given by JEFF-3.3 for the electromagnetic heat around this time, as shown in Fig. 7.
A comparison of the 40 dominant contributors is shown in Fig. 10 for the light particle decay heat. These nuclides were sorted according to their contributions obtained using the ENDF/B-VIII.0 Set-A. In all cases, over 80% of the light-particle decay heat was provided by these 40 nuclides at the cooling time of 10 s. In contrast to the reasonable agreement in HLP, visible divergences occurred among the contributions of important fission products obtained using the different evaluated libraries. In particular, the contributions of 102Nb, 96mY, and 146mLa calculated using JENDL-5 were less than half of those calculated with ENDF/B-VIII.0 and JEFF-3.3, no matter the set of data used. In addition, the adjustment of IFYs has a weak influence on the contributions of ENDF/B-VIII.0 and JEFF-3.3, whereas the contributions of some specific nuclides are clearly affected by JENDL-5, such as 97Y, 135Te, 137,138I, and 89Br.
_2026_06/1001-8042-2026-06-101/alternativeImage/1001-8042-2026-06-101-F010.jpg)
More significant divergences were observed in the electromagnetic decay heat, as shown in Fig. 11. These 40 nuclides were the most significant contributors to the calculations using the ENDF/B-VIII.0 Set-A, and their total contribution accounted for over 75% of the electromagnetic decay heat in all cases. Notably, 98Zr does not contribute to electromagnetic heat if the decay data of JENDL-5 or JEFF-3.3 are used, whereas it contributes 0.8% in the calculations with ENDF/B-VIII.0. This is because
_2026_06/1001-8042-2026-06-101/alternativeImage/1001-8042-2026-06-101-F011.jpg)
The relative sensitivity coefficient of the decay heat (H) to nuclear data (x) is defined as_2026_06/1001-8042-2026-06-101/alternativeImage/1001-8042-2026-06-101-M016.png)
The compositions of sH(YI) are listed in Tables 2 and 3 for the important fission products presented in Figs. 10 and 11 respectively. The nuclide is omitted if its sH(YI) is smaller than 0.01 in all calculations. In general, 100Zr and 93Rb had the highest relative sensitivity coefficients for light particles and electromagnetic decay heat, respectively, among the three evaluated libraries. The relative changes owing to the yield adjustment were smaller than 20% for sH(YI) for the two types of decay heat in most cases, revealing a weak influence. However, dramatic changes were observed in the relative sensitivity coefficients of the electromagnetic decay heat calculated using the JENDL-5. For example, the coefficient of 96mY is enhanced by approximately five times after GLS updating process, whereas those of 102Nb and 146La are reduced by approximately 95% and 65%, respectively.
| Nuclide | ENDF/B-VIII.0 | JENDL-5 | JEFF-3.3 | |||
|---|---|---|---|---|---|---|
| Set-A | Set-B | Set-A | Set-B | Set-A | Set-B | |
| 96Y | - | - | 2.02 | 1.73 | - | - |
| 92Rb | 3.64 | 3.59 | 4.81 | 4.41 | 3.58 | 3.57 |
| 101Nb | 1.70 | 1.67 | 1.78 | 1.89 | 1.37 | 1.34 |
| 93Rb | 2.98 | 2.94 | 3.88 | 3.64 | 2.50 | 2.48 |
| 100Zr | 10.13 | 9.78 | 9.40 | 9.06 | 9.01 | 9.01 |
| 91Kr | 3.48 | 3.43 | 3.46 | 3.58 | 3.36 | 3.35 |
| 95Sr | 2.31 | 2.32 | 2.31 | 2.38 | 2.25 | 2.24 |
| 135Te | 2.41 | 2.39 | 2.02 | 2.15 | 2.52 | 2.62 |
| 97Y | 1.21 | 1.17 | - | - | - | - |
| 143Ba | 1.81 | 1.82 | 1.89 | 1.84 | 1.70 | 1.70 |
| 99Zr | 2.27 | 2.20 | 2.45 | 2.27 | 2.27 | 2.25 |
| 146La | - | - | 1.25 | 1.18 | - | - |
| 138I | 1.59 | 1.59 | 2.11 | 2.38 | 1.48 | 1.49 |
| 141Cs | 1.15 | 1.15 | 1.36 | 1.39 | 1.11 | 1.10 |
| 139Xe | 1.43 | 1.41 | 1.32 | 1.26 | 1.32 | 1.32 |
| 144Ba | 1.81 | 1.79 | 1.85 | 1.85 | 1.85 | 1.85 |
| 140Xe | 1.80 | 1.80 | 1.57 | 1.49 | 2.24 | 2.23 |
| 137I | 1.36 | 1.38 | 1.58 | 1.74 | 1.31 | 1.34 |
| 96mY | 1.42 | 1.35 | - | - | - | - |
| 90Kr | 1.36 | 1.35 | 1.17 | 1.16 | 1.26 | 1.26 |
| 101Zr | 4.29 | 4.23 | 4.62 | 4.27 | 4.48 | 4.51 |
| 145Ba | 1.45 | 1.47 | 1.44 | 1.49 | 1.57 | 1.57 |
| 87Se | 1.12 | 1.09 | - | - | - | - |
| 102Zr | 3.65 | 3.61 | 2.76 | 2.64 | 2.78 | 2.81 |
| 89Br | - | - | 1.21 | 1.39 | - | - |
| 98Zr | 1.48 | 1.28 | 1.39 | 1.20 | 1.65 | 1.63 |
| 94Rb | - | - | 1.27 | 1.23 | - | - |
| 147La | - | - | 1.11 | 1.07 | - | - |
| Nuclide | ENDF/B-VIII.0 | JENDL-5 | JEFF-3.3 | |||
|---|---|---|---|---|---|---|
| Set-A | Set-B | Set-A | Set-B | Set-A | Set-B | |
| 92Rb | 3.77 | 3.72 | - | - | - | - |
| 93Rb | 4.90 | 4.85 | 6.16 | 4.79 | 6.16 | 5.78 |
| 96mY | 5.19 | 4.95 | 0.68 | 3.28 | - | - |
| 102Nb | - | - | 1.60 | 0.10 | 1.60 | 1.71 |
| 143Ba | 2.78 | 2.80 | 2.76 | 2.93 | 2.76 | 2.69 |
| 91Kr | 4.27 | 4.22 | 4.22 | 4.48 | 4.22 | 4.36 |
| 95Sr | 3.02 | 3.04 | 2.89 | 3.25 | 2.89 | 2.97 |
| 97Y | 1.41 | 1.37 | - | - | - | - |
| 145La | 1.50 | 1.46 | 1.36 | 1.07 | 1.36 | 1.25 |
| 88Br | 2.06 | 2.04 | 3.28 | 2.61 | 3.28 | 3.38 |
| 141Cs | 1.79 | 1.79 | 2.02 | 1.92 | 2.02 | 2.07 |
| 144La | 2.50 | 2.50 | 2.01 | 3.42 | 2.01 | 1.91 |
| 91Rb | 1.08 | 1.06 | 1.07 | 1.13 | 1.07 | 0.97 |
| 144Ba | 3.25 | 3.22 | 3.13 | 3.61 | 3.13 | 3.14 |
| 145Ba | 3.16 | 3.21 | 3.27 | 4.30 | 3.27 | 3.39 |
| 90Kr | 1.85 | 1.84 | 2.29 | 1.92 | 2.29 | 2.27 |
| 99Zr | 1.06 | 1.03 | 1.06 | 1.23 | 1.06 | 0.98 |
| 146La | - | - | 1.06 | 0.37 | 1.06 | 1.00 |
| 86Se | 1.18 | 1.17 | 1.65 | 1.15 | 1.65 | 1.56 |
| 138I | 1.27 | 1.27 | 1.38 | 1.13 | 1.38 | 1.56 |
| 136Te | 1.35 | 1.46 | 1.15 | 1.83 | 1.15 | 1.35 |
| 139Xe | 1.11 | 1.09 | 1.45 | 1.20 | 1.45 | 1.38 |
| 137I | 1.08 | 1.10 | 1.30 | 1.32 | 1.30 | 1.43 |
| 94Sr | - | - | 0.83 | 1.02 | - | - |
| 87Br | - | - | 1.07 | 1.02 | 1.07 | 1.06 |
| 149Ce | 1.07 | 1.07 | - | - | - | - |
| 94Rb | 1.28 | 1.27 | 2.80 | 2.35 | 2.80 | 2.72 |
| 89Br | 1.02 | 1.02 | 1.92 | 1.05 | 1.92 | 2.21 |
| 146mLa | - | - | 0.87 | 1.18 | - | - |
| 100Zr | 3.53 | 3.41 | 5.74 | 3.51 | 5.74 | 5.53 |
Summary and conclusions
The generalized least-squares updating approach was implemented in the covariance generation for 235U(nth,f) independent fission yields in the widely used nuclear data libraries ENDF/B-VIII.0, JENDL-5, and JEFF-3.3, with constraints on the basic physical conservation equation and chain yield data. The variances of the original IFYs were strongly reduced and reintroduced as correlations between IFYs, which were mainly negative correlations. The yield data were also slightly adjusted during GLS updating process.
The original and updated IFYs as well as decay data were used in the uncertainty analyses of decay heat using the generalized perturbation theory, including the uncertainties propagated from the yield and decay data. Good agreement on the decay heat was achieved by the three libraries at cooling times longer than 1000 s. However, discrepancies were found within 1000 s, and a significant underestimation was caused by JEFF-3.3, for electromagnetic decay heat from 5 to 50 s. The adjustment of IFYs had a weak influence on the decay heat, whereas the generated correlation strongly reduced the contribution of the yield data to the decay heat uncertainty. Using the updated yield data with covariance matrixes, the uncertainties of decay heat are ~10% for ENDF/V-VIII.0 and JEFF-3.3 and ~5% for JENDL-5 at cooling time 0.1 s, which are approximately 1% for the three libraries at 105 s, mainly coming from decay energy data. The influence of yield data adjustment on the decay heat contributions of important fission products and their sensitivity coefficients was also investigated. Evidently, the influence was small for ENDF/B-VIII.0 and JEFF-3.3, while noticeable changes occurred on some important fission products for JENDL-5.
The validity of the present fission yield covariance generation approach was justified, and the updated fission yield data are expected to be applicable in nuclear design and safety analysis together with their covariance matrixes.
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