Introduction
Reliable knowledge of neutron-induced cross-sections (CSs) is required in nuclear power plants for energy and environmental protection, and in nuclear astrophysics reaction network calculations for vital input parameters [1-5]. Accurate measurements of CSs induced by neutrons at 14 MeV are desired for fusion reactors, nuclear transmutation, and nuclear model analyses [6-8]. Xe has nine stable isotopes [9]; 14-MeV neutrons can trigger nuclear reactions of Xe isotopes, including (n,α), (n,d), (n,p), (n,t), and (n,2n) [10,11]. The 134Xe(n,2n)133m,gXe CSs for such reactions were experimentally obtained by two laboratories [12,13] using sodium perxenate (Na4XeO6·2H2O) and quinol clathrate targets, respectively. In general, preparation of this compound is complicated; the composition is complex, and it is difficult to ensure purity (Ref. (12) reported an Na4XeO6·2H2O purity of 95.8%. Only one laboratory reported pure ground-state CSs in the 134Xe(n,2n)133gXe reaction [12]. The excited-state, ground-state, total CS, and CS ratio for 134Xe(n,2n)133m,gXe reactions correspond to a single energy value (14.4 MeV or 14.6 MeV). Extensive research on the excitation functions for 124,126,128,130,132,136Xe(n, 2n) and 130,131,132Xe(n, p) reactions in the range of 13-15 MeV was recently reported by Bhatia et al. [14], Bhike et al. [15,16], and Luo et al. [17,18].
Our goal was to analyze four aspects of the 134Xe(n,2n) reaction CS. First, the target 134Xe isotope belongs to a transitional region (N = 82, below the closed neutron shell); an even 134Xe nucleus for such shell closure is a good indicator of single-particle excitations [17]. Second, the half-life of the metastable state of the 133m,gXe pair is shorter than that of the ground state. This pair exhibits isomeric transition (IT) decay (Fig. 1). Third, published data on the 134Xe(n,2n) reaction CS are scarce owing to difficulties in preparing gaseous targets for irradiation. Fourth, significant discrepancies have been observed in published results [12,13], mainly due to the following three factors:
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i. Systematic inconsistencies are caused by differences in experimental techniques and conditions (neutron field characteristics, target sample, neutron monitoring method). Previous studies have used sodium perxenate (Na4XeO6·2H2O) and the solid quinol clathrate of Xe as the target materials [12, 13]. For neutron flux monitoring, Sigg and Kuroda (1976) [12] used a low-threshold reaction: 27Al(n,α)24Na (Eth=3.25 MeV). Kondaiah et al. (1968) [13] used 136Xe(n,2n)135(m+g)Xe and 128Xe(n,2n)127(m+g)Xe reactions to monitor 134Xe(n,2n)133mXe and 134Xe(n,2n)133(m+g)Xe nuclear reactions (Table 1).
Reaction | Decay data | Sample | Detector | Monitor reaction | En (MeV) | σ (mb) | Ref. | |
---|---|---|---|---|---|---|---|---|
134Xe(n,2n)133mXe | T 1/2=2.26 d, Eγ=232.8 keV, Iγ=14 % | Na4XeO6·2H2O | GeLi | 27Al(n,α)24Na | 14.6 | 655±60 | 906±83a | [12] |
T1/2=2.26 d, Eγ=233 keV, Iγ=13.55 % | Quinol clathrate | GeLi | 136Xe(n,2n)135(m+g)Xe | 14.4 | 665±80 | 890±107a | [13] | |
134Xe(n,2n)133gXe | T1/2=5.29 d, Eγ=81.0 keV, Iγ= 35% | Na4XeO6·2H2O | GeLi | 27Al(n,α)24Na | 14.614.4 | 805±901695±226b | 755±84a1366±202b | [12][13] |
134Xe(n,2n)133m+gXe | T 1/2=5.29 d, Eγ=81.0 keV, Iγ= 35% | Na4XeO6·2H2O | GeLi | 27Al(n,α)24Na | 14.6 | 1460±110 | 1661±118a | [12] |
T1/2=5.27 d, Eγ=81 keV, Iγ= 35.7% | Quinol clathrate | GeLi | 128Xe(n,2n)127(m+g)Xe | 14.4 | 2360±240 | 2256±229a | [13] |
ii. There is a significant shortage of decay data. The 134Xe(n,2n)133mXe reaction CSs [12, 13] exhibited characteristic γ-ray intensities (14% and 13.55% at 233 keV, respectively (Table 1)). Recently, 10.12% was also reported [9]. The 134Xe(n,2n)133gXe reaction CSs were measured by Sigg and Kuroda (1976) [12], and Kondaiah et al. (1968) [13] using characteristic γ-ray intensities of 35% and 35.7%, respectively, for the same characteristic γ-ray of 81 keV (Table 1). However, 36.9% was obtained more recently [9]. As 79.61 keV and 80.998 keV γ-ray energies are so close that they cannot be distinguished by the detector, the intensity of the 81-keV gamma ray should be higher (37.34% = 0.44% + 36.9%). The CS of 133mXe radionuclide product with a 2.26-d half-life was also determined [12, 13], recently reported as 2.198 d [9].
iii. There are differences in the total CS measurement methods. Only two methods currently exist for calculating the total CS. 1) The excited-state and pure ground-state CSs can be added after measuring them separately [12]. 2) The ground state can be measured after full decay of the excited state via IT, and the result can be considered as the total CS [13]. The latter method satisfies the conditions that the excited-state half-life is less than that of the ground state, preferably much less, and IT = 100%. If these conditions are not satisfied, it is not advisable to replace the total CS with the obtained ground-state CS.
Analysis of the existing data led us to conclude that the isomeric ratios (IRs) and CSs for the (n,2n) reaction of 134Xe in the 13–15 MeV range must be further analyzed. We used residual nuclear decay analysis [19-21] and natural Xe with high-purity pressure as the target to measure the 134Xe(n,2n)133mXe, 134Xe(n,2n)133gXe, and 134Xe(n,2n)133Xe CSs reactions and their corresponding isomeric-state CSs in the 13-15 MeV range. The results were compared with theoretical values obtained using TALYS-1.95 [22], evaluation data, and previous experimental results.
Experimental Methods
Sample preparation
Naturally pure Xe (99.999%, 2.3–5.2 g) pressurized to 120–250 atm was placed in a 1-mm thick spherical stainless steel container 20 mm in diameter. The samples and monitors (niobium foil: Φ = 20 mm, 0.12-mm thick, 99.99% pure; aluminum foil: Φ = 20 mm, 0.3-mm thick,99.999% pure), and zirconium foil (Φ = 20 mm, 0.2-mm thick, 99.95% pure) were combined as ZrNbAl-Xe-AlNbZr for irradiation. The samples were mounted at different angles (0º, 45º, 90º, 110º, 135º) to the incident beam. The neutron-producing target edge was 5 cm from the sample center. Due to its high threshold energy, the 93Nb(n,2n)92mNb (threshold energy 8.972 MeV) reaction was used to monitor the corresponding threshold energies of 134Xe(n,2n)133m,gXe reactions (Eth = 8.853 MeV and 8.618 MeV). Low-threshold reactions such as (n,α) and (n,p) were monitored via a 27Al(n,α)24Na reaction (threshold energy = 3.249 MeV). The CS of the 93Nb(n,2n)92mNb reaction was obtained from the IRDFF-II data library [23]. To minimize the influence of the 132Xe(n,γ)133m,gXe reaction on the 134Xe(n,2n)133m,gXe reaction, the samples were covered with Cd foil (1-mm thick, 99.95% pure). The details of this approach are presented in our previous studies [17,18].
The neutron generator facility was provided by the China Academy of Engineering Physics (CAEP) for sample irradiation at (4-5)×1010 n/s yield (for 2 h). The d+3H→n+4He+17.6 MeV reaction provided neutrons at 14 MeV with deuteron beam current and energy of 200 μA and 134 keV, respectively. The tritium–titanium target thickness was 2.65 mg/cm2. A beam of α-particles at 135° was used to correct the neutron flux.
Neutron energy and detection efficiency
In the experiment, Zr and Nb were used to measure the CS ratios of 93Nb(n,2n)92mNb and 90Zr(n,2n)89m+gZr, respectively, to determine the neutron energy. At irradiation angles of 135°, 110°, 90°, 45°, and 0°, the energies were 13.5 MeV, 13.8 MeV, 14.1 MeV, 14.4 MeV, and 14.8 MeV, respectively. For verification purposes, the neutron energies were determined using different methods [24]. Considering the sample distance from the target, size, and beam radius, the uncertainty in the neutron energy was 0.2 MeV [25]. The results obtained using the CS ratio method were consistent in terms of the experimental errors. The detector efficiency was calibrated using 152Eu, 133Ba, 137Cs, and 226Ra standard sources. The Monte Carlo method was used to adjust the data for the geometrical differences between the calibration sources applied to the HPGe detector and the Xe sphere efficiency determination. The details are provided in our previous studies [17,18].
Radioactivity measurement
Five samples (No.1–5) were allowed to decay after irradiation for 2.9 d, 3.9 d, 5.0 d, 4.0 d, and 5.0 d, respectively. The γ-ray activities of 133mXe, 133gXe, and 92mNb nuclei were measured with a coaxial HPGe detector, with crystal diameter, length, relative efficiencies, and energy resolution (1.332 MeV) of 70.1 mm, 72.3 mm, 68%, and 1.69 keV, respectively. Typical γ-ray spectra obtained after 2.9 d of irradiation are shown in Fig. 2. A γ-spectrum analysis was performed using ORTEC® GammaVision® software to estimate the peak area [26].
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Table 2 displays the natural isotope abundance and product decay characteristics.
Isotope Abundance (%) | Reaction | E-threshold (MeV) | Mode decay (%) | Product half-life | Eγ (keV) | Iγ (%) |
---|---|---|---|---|---|---|
10.435721 | 134Xe(n,2n)133mXe | 8.853 | IT(100) | 2.198 d13 | 233.22 | 10.1215 |
10.435721 | 134Xe(n,2n)133gXe | 8.618 | β-(100) | 5.2475 d5 | 80.99879.61 | 36.930.4418 |
100 | 93Nb(n,2n)92mNb | 8.972 | EC (100) | 10.15 d2 | 934.44 | 99.154 |
CS calculations and associated uncertainties
CS calculation
The reaction CSs can be expressed as [17, 18]
Gamma-ray energy (keV) | μ/ρ (cm2/g) | μ(cm-1) | Sample density ρ (g/cm3) | Correction factor fs | |||
---|---|---|---|---|---|---|---|
Fe | Xe | Fe | No. | Xe | |||
80.998 | 0.5840 | 3.5521 | 4.5906 | 1 | 4.4117 | 1.2420 | 8.288 |
2 | 2.0804 | 0.5857 | 4.103 | ||||
3 | 4.2326 | 1.1916 | 7.956 | ||||
4 | 1.9529 | 0.5498 | 3.889 | ||||
5 | 1.9369 | 0.5453 | 3.863 | ||||
233.22 | 0.1340 | 0.3108 | 1.0533 | 1 | 0.3860 | 1.2420 | 1.390 |
2 | 0.1820 | 0.5857 | 1.204 | ||||
3 | 0.3703 | 1.1916 | 1.375 | ||||
4 | 0.1709 | 0.5498 | 1.195 | ||||
5 | 0.1695 | 0.5453 | 1.194 |
To obtain the pure ground-state CSs for 134Xe(n,2n)133gXe reactions, Cx in Equation (1) was set to a peak area of 80.998 keV minus the contribution from 133mXe via
Associated experimental uncertainties
When calculating the main uncertainties of CS determination, we assumed that only the half-life uncertainty contributed to the uncertainty in the timing factor. The following parameters were used for this purpose: Cx,Nb as the γ-ray counting statistics, Mx,Nb as the target masses, Ix,Nb as the relative γ-ray intensities, ηx, as the target isotopic abundance, σNb as the standard CS, εx,Nb as the efficiencies, and Sx,Nb, and Dx,Nb as timing factors. The subscripts Nb and x correspond to the monitored and measured reaction-related terms, respectively.
For generative nuclei 133mXe and 133gXe, the uncertainty of correction factor F is estimated as 2.0% and 3.0%, respectively. These uncertainties were applied to assess the total uncertainty of the experimental CSs [27-30]. Table 4 and Table 5 highlight the uncertainties in the parameters contributing to the reaction CS values, which were used to extend the covariance matrix between different energy levels. All samples were investigated using the same setup and standard CS reaction. Thus, the detector efficiency and standard CS accuracy were consistent for all neutron energy correlations. After calculation of fractional uncertainties, covariance analysis calculated the correlation coefficients between each energy-related property. The coefficients and corresponding energies are presented in Table 6. The CS covariance matrix and total uncertainty were generated for energy-level pairs (e.g., (σxi,σxj)) using the data from Tables 4-6 by adding 15 subset matrices in Equation 4 [29]:
Attributes (x) | Fractional uncertainties (%) | ||||
---|---|---|---|---|---|
13.5 MeV(Δxi) | 13.8 MeV(Δxj) | 14.1 MeV(Δxk) | 14.4 MeV(Δxl) | 14.8 MeV(Δxn) | |
Cx | 0.1236 | 0.1471 | 0.1349 | 0.1750 | 0.0726 |
CNb | 0.8523 | 0.8102 | 0.8083 | 0.8164 | 0.9315 |
Ix | 1.4822 | 1.4822 | 1.4822 | 1.4822 | 1.4822 |
INb | 0.0403 | 0.0403 | 0.0403 | 0.0403 | 0.0403 |
Mx | 0.0401 | 0.0869 | 0.0816 | 0.0876 | 0.0385 |
MNb | 0.0111 | 0.0109 | 0.0112 | 0.0110 | 0.0112 |
ηx | 0.0201 | 0.0201 | 0.0201 | 0.0201 | 0.0201 |
σNb | 0.6327 | 0.5615 | 0.5461 | 0.5427 | 0.5645 |
εx | 2.7201 | 2.7201 | 2.7201 | 2.7201 | 2.7201 |
εNb | 2.5038 | 2.5038 | 2.5038 | 2.5038 | 2.5038 |
Sx | 0.5836 | 0.5836 | 0.5836 | 0.5836 | 0.5836 |
SNb | 0.1965 | 0.1965 | 0.1965 | 0.1965 | 0.1965 |
Dx | 0.4188 | 0.4197 | 0.2302 | 0.2335 | 0.0419 |
DNb | 0.1857 | 0.1857 | 0.1858 | 0.1858 | 0.1860 |
Fx | 2.0000 | 2.0000 | 2.0000 | 2.0000 | 2.0000 |
Total error (%) | 4.65 | 4.63 | 4.62 | 4.62 | 4.63 |
Attributes (x) | Fractional uncertainties (%) | ||||
---|---|---|---|---|---|
13.5 MeV(Δxi) | 13.8 MeV(Δxj) | 14.1 MeV(Δxk) | 14.4 MeV(Δxl) | 14.8 MeV(Δxn) | |
Cx | 0.1198 | 0.1224 | 0.1115 | 0.1174 | 0.0936 |
CNb | 0.8523 | 0.8102 | 0.8083 | 0.8164 | 0.9315 |
Ix | 1.2854 | 1.2854 | 1.2854 | 1.2854 | 1.2854 |
INb | 0.0403 | 0.0403 | 0.0403 | 0.0403 | 0.0403 |
Mx | 0.0201 | 0.0869 | 0.0816 | 0.0876 | 0.0385 |
MNb | 0.0111 | 0.0109 | 0.0112 | 0.0110 | 0.0112 |
ηx | 0.0201 | 0.0201 | 0.0201 | 0.0201 | 0.0201 |
σNb | 0.6327 | 0.5615 | 0.5461 | 0.5427 | 0.5645 |
εx | 3.9743 | 3.9743 | 3.9743 | 3.9743 | 3.9743 |
εNb | 2.5038 | 2.5038 | 2.5038 | 2.5038 | 2.5038 |
Sx | 0.0094 | 0.0094 | 0.0094 | 0.0094 | 0.0094 |
SNb | 0.1965 | 0.1965 | 0.1965 | 0.1965 | 0.1965 |
Dx | 0.0027 | 0.0039 | 0.0039 | 0.0039 | 0.0052 |
DNb | 0.1857 | 0.1857 | 0.1858 | 0.1858 | 0.1860 |
Fx | 3.0000 | 3.0000 | 3.0000 | 3.0000 | 3.0000 |
Total error (%) | 5.83 | 5.82 | 5.82 | 5.82 | 5.83 |
Cor(Δx, Δx) | Correlation coefficient (Δx, Δx) | |||||||
---|---|---|---|---|---|---|---|---|
Cx | CNb | Mx | MNb | εx | Sx | Dx | Fx | |
(Δxi, Δxi) | 1 | 1 | 1 | 1 | 1 | 1 | 1 | 1 |
(Δxi, Δxj) | 0 | 0 | 0 | 0 | 0.9987 | 0 | 0 | 0 |
(Δxi, Δxk) | 0 | 0 | 0 | 0 | 0.9987 | 0 | 0 | 0 |
(Δxi, Δxl) | 0 | 0 | 0 | 0 | 0.9987 | 0 | 0 | 0 |
(Δxi, Δxn) | 0 | 0 | 0 | 0 | 0.9987 | 0 | 0 | 0 |
(Δxj, Δxj) | 1 | 1 | 1 | 1 | 1 | 1 | 1 | 1 |
(Δxj, Δxk) | 0 | 0 | 0 | 0 | 0.9987 | 0 | 0 | 0 |
(Δxj, Δxl) | 0 | 0 | 0 | 0 | 0.9987 | 0 | 0 | 0 |
(Δxj, Δxn) | 0 | 0 | 0 | 0 | 0.9987 | 0 | 0 | 0 |
(Δxk, Δk) | 1 | 1 | 1 | 1 | 1 | 1 | 1 | 1 |
(Δxk, Δxl) | 0 | 0 | 0 | 0 | 0.9987 | 0 | 0 | 0 |
(Δxk, Δxn) | 0 | 0 | 0 | 0 | 0.9987 | 0 | 0 | 0 |
(Δxl, Δxl) | 1 | 1 | 1 | 1 | 1 | 1 | 1 | 1 |
(Δxl, Δxn) | 0 | 0 | 0 | 0 | 0.9987 | 0 | 0 | 0 |
(Δxn, Δxn) | 1 | 1 | 1 | 1 | 1 | 1 | 1 | 1 |
The generated covariance matrix was [5×5]. The uncertainty in the experimental CS value was determined as (Equation 5) [29]
From the covariance matrix and total uncertainty between neutron energies, the correlation matrix [5×5] was derived using Eq. 6 [29]:
The experimentally obtained reaction CS values and their correlation matrices and uncertainties are presented in Table 7 and Table 8.
Neutron energyEn (MeV) | Cross-sectionσx (mb) | Δσx (%) | Correlation matrix | ||||
---|---|---|---|---|---|---|---|
13.5±0.2 | 884±41 | 4.65 | 1.0000 | ||||
13.8±0.2 | 888±41 | 4.63 | 0.7565 | 1.0000 | |||
14.1±0.2 | 909±42 | 4.62 | 0.7586 | 0.7593 | 1.0000 | ||
14.4±0.2 | 916±42 | 4.62 | 0.7581 | 0.7588 | 0.7610 | 1.0000 | |
14.8±0.2 | 928±43 | 4.63 | 0.7562 | 0.7569 | 0.7591 | 0.7586 | 1.0000 |
Neutron energyEn (MeV) | Cross-sectionσx (mb) | Δσx (%) | Correlation matrix | ||||
---|---|---|---|---|---|---|---|
13.5±0.2 | 824±48 | 5.83 | 1.0000 | ||||
13.8±0.2 | 810±47 | 5.82 | 0.7125 | 1.0000 | |||
14.1±0.2 | 786±46 | 5.82 | 0.7125 | 0.7129 | 1.0000 | ||
14.4±0.2 | 767±45 | 5.82 | 0.7123 | 0.7127 | 0.7127 | 1.0000 | |
14.8±0.2 | 747±44 | 5.83 | 0.7105 | 0.7108 | 0.7108 | 0.7106 | 1.0000 |
Table 9 shows experimental values for 134Xe(n,2n)133m+gXe reaction CSs and their IRs, and the monitor reaction CSs at different neutron energies.
En (MeV) | This study | Monitor reaction 93Nb(n,2n)92mNb | ||
---|---|---|---|---|
CS (mb) | IRs (σm/σg) | CS (mb) | Reference | |
13.5±0.2 | 1708±63 | 1.07±0.08 | 453.0±2.9 | [24] |
13.8±0.2 | 1698±63 | 1.10±0.08 | 457.4±2.6 | [24] |
14.1±0.2 | 1696±62 | 1.16±0.09 | 459.7±2.5 | [24] |
14.4±0.2 | 1683±62 | 1.20±0.09 | 460.1±2.5 | [24] |
14.8±0.2 | 1675±61 | 1.24±0.09 | 460.2±2.6 | [24] |
Theoretical calculations
TALYS software is widely used to analyze pre-equilibrium mechanisms, direct nuclear reactions, and compound nuclei (CN). It can evaluate nuclear reactions in the range of 0.001–200 MeV for target nuclei with masses of 12 and higher. TALYS also calculates the nuclear reaction CSs. Theoretical calculations for different ratios of 134Xe(n,2n)133m,gXe reactions (σm/σg) were performed for different ranges of neutron energies using TALYS-1.95 (ver. 1.95) [22]. We used the default parameters for our calculations, except for six distinct nuclear level density models (NLDs), which were divided into two groups: three microscopic levels and three phenomenological densities. The phenomenological level densities included: 1) ldmodel 1, with a constant temperature and Fermi gas model, and excitation energy divided into higher and lower energy regions in the Fermi gas model and with constant temperature laws, respectively; 2) ldmodel 2 is based on the back-shifted Fermi gas model, which uses the Fermi gas expression across the region; 3) ldmodel 3 is a generalized superfluid model that considers superconductive correlations based on Barden-Cooper-Schrieffer theory [31-32]. The microscopic level densities are i) ldmodel 4 is made up of Goriely's tables derived from the Skyrme force (microscopic level densities) [33]; ii) ldmodel 5 consists of Hilaire’s combinatorial tables derived from the Skyrme force [33]; iii) ldmodel 6 is the Gogny force, derived from Hilaire’s combinatorial tables [33]. Examining the spin distribution is feasible using relative feeding as a ‘probe’.
Results and discussion
Tables 7, 8 and 9 show the CSs of the 134Xe(n,2n)133mXe, 134Xe(n,2n)133gXe, and 134Xe(n,2n)133Xe reactions and the corresponding isomeric-state CS ratios obtained using the activation method. The data of the excited state and pure ground state were compared to data from the literature [12,13] and data obtained by TALYS-1.95 at six energy-level densities [22]. The 134Xe(n,2n)133Xe CS was also compared to data from the ENDF/B-VIII.0 [35], JEFF-3.3 [36], JENDL-4.0 [37], ROSFOND [38], and CENDL-3 [39] databases.
134Xe(n,2n)133mXe reaction
Two studies [12,13] have reported 134Xe(n,2n) experiments for the 133mXe reaction. However, they provide the CS at only one energy value (14.4 MeV or 14.6 MeV). For a γ-ray with 233.22 keV energy, Sigg and Kuroda [12] used Iγ□ = 14%, and Kondaiah et al. [13] used Iγ□ = 13.6%. However, other studies indicate that data measurement accuracy was higher with Iγ□ = 10.12%. In this study, γ-ray energy of 233.22 keV with an intensity of Iγ□ = 10.12% emitted during the decay of 133mXe was used to obtain the 134Xe(n,2n)133mXe reaction CS. Thus, the CS values were modified according to the following equation:
-202301/1001-8042-34-01-004/alternativeImage/1001-8042-34-01-004-F003.jpg)
134Xe(n,2n)133gXe reaction
A thorough literature review yielded only one measurement of the 134Xe(n,2n)133gXe reaction using γ-ray energy of 81 keV (Iγ□ = 35%) [12]. However, many investigations have used Iγ□ = 36.9% for gamma-rays with the same energy. Production of the 133gXe nucleus resulted in two characteristic gamma-rays with similar energies, 79.61 keV (Iγ□ = 0.44%) and 80.998 keV (Iγ□ = 36.9%). Our detectors could not resolve these energies; the intensity should be equal to their sum (37.34%). Accordingly, Equation (8) was used to modify the CS values from Ref. [12]. During the 133m,gXe decay, the emitted 80.998-keV γ-ray was used to calculate the 134Xe(n,2n)133gXe reaction CSs after subtracting the contribution of the 134Xe(n,2n)133mXe reaction via the isomeric transition (IT). Almost 50% of the 80.998-keV γ-ray counts were from the isomeric transitions. Figure 4 shows the theoretical assessments of the excitation functions and the experimental results (Ref. [13] does not provide ground-state CS values, which are equal to the total CS value minus the excited-state CS value.). The measured values exceeded those calculated using the TALYS-1.95 software with ldmodels 1-6. However, our experimental and theoretical results show the same dependence on neutron energy. At 14.6 MeV, our measurements agreed with the corrected values obtained by Sigg and Kuroda [12]. At 14.4 MeV, the results in Ref. [13] significantly exceeded our experimental and simulated results (using TALYS-1.95, ldmodels 1-6). For this reaction, the CS values span a wide energy range.
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134Xe(n,2n)133Xe reaction
There are two published reports on the 134Xe(n,2n)133Xe reaction at a neutron energy of 14 MeV that can be used to validate theoretical calculations and experimental results. The shapes of the excitation curves obtained from the ENDF/B-VIII.0 [35], (JEFF-3.3 [36], CENDL-3 [39]), JENDL-4.0 [37], and ROSFOND [38] databases were almost identical to those obtained by TALYS-1.95 [22] at ~15 MeV (Fig. 5). We conclude that the experimental data agree with the ROSFOND [38] results, TALYS-1.95 with ldmodel 1, and the corrected experimental results of Sigg and Kuroda [12]. At 14.4 MeV, the values [13] were 570 mb higher than ours. The evaluation excitation curve taken from JENDL-4.0 [37] is above the corrected results of Sigg and Kuroda [12], our experimental results, and results from the other databases [35,36,38,39]. Data for the 13.5-14.1 MeV neutron energy range are reported for the first time.
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Isomeric CS ratio
The ratios of the isomeric CSs were calculated using the measured 134Xe(n,2n)133m.gXe CSs. The CS ratios (σm/σg) for the isomeric 133m,gXe pair created from the 134Xe(n,2n) reaction exposed to incident neutrons with energies of 13.5 ± 0.2 MeV, 13.8 ± 0.2 MeV, 14.1 ± 0.2 MeV, 14.4 ± 0.2 MeV, and 14.8 ± 0.2 MeV are 1.07 ± 0.08, 1.10 ± 0.08, 1.16 ± 0.09, 1.20 ± 0.09, and 1.24 ± 0.09, respectively (Table 9). Figure 6 shows the corrected isomeric CS ratios from the literature [12,13] and the excitation curves obtained using TALYS-1.95 calculations for different density-level models. The isomeric CS ratios increased with energy. In the 14-MeV region, the isomeric CS ratio is directly correlated with the neutron energy, indicating that higher excitation energies result in high-spin isomers (11/2-→3/2+) [40-43]. The obtained σm/σg values were consistent with the modified values from Sigg and Kuroda [12], but slightly lower than the values obtained using ldmodels 1-6 and higher than the results of Ref. [13]. Our data for neutrons with 13.5-14.1 MeV energies are the first available in the literature to the best of our knowledge.
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Summary and Conclusions
The σm, σg, and σm+g for the 134Xe(n,2n)133mXe, 134Xe(n,2n)133gXe, and 134Xe(n,2n)133Xe reactions and the corresponding isomeric CS ratios (σm/σg) were determined from the neutron activation and offline γ–ray spectra of the residual products at 13.5–14.8 MeV using the 93Nb(n,2n)92mNb reaction as a reference. We thoroughly analyzed the uncertainties of the experimentally obtained CSs using covariance analysis. Experimental data were compared to data from the literature and CS values obtained using TALYS-1.95 software and from the ENDF/B-VIII.0, JEFF-3.3, JENDL-4.0, ROSFOND, and CENDL-3 databases. The theoretically obtained CS values for the 134Xe(n,2n) reaction at six different NLDs (to generate nuclear excited and ground states) disagreed with the experimental results. However, the total CSs values were in agreement. The magnitude of the calculated CSs differed due to variations in the nuclear inputs and reaction models used for the simulations. The reaction mechanism involves photon and particle emissions in the CN. The CN CS is determined by the OPs, NLDs, and γSFs. Significant discrepancies were found in the experimental values; however, these were observed only for the pure ground state and total CSs as they are the most affected by the excited states. The CSs at neutron energies of 13.5–14.1 MeV are presented for the first time for the 134Xe(n,2n)133mXe, 134Xe(n,2n)133gXe, and 134Xe(n,2n)133Xe reactions, significantly extending the currently published energy ranges. These values can benefit nuclear databases for exploring fundamental nuclear applications and nuclear reaction models.
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