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The experiments were performed by measuring the residual γ-activity of the irradiated sample, which enables simultaneous acquisition of data on different channels of the photonuclear reactions. This method is well known and has been described in several studies on multiparticle photonuclear reactions, for example, on the 93Nb nucleus [29, 30].
The block diagram of the experiment is shown in Fig. 1, similar to that in [29]. Electrons from the NSC KIPT electron linear accelerator LUE-40 [31, 32] with an initial energy
$ E_{\rm{e}} $ are incident on the target-convertor made of natural tantalum with cross dimensions of 20 mm × 20 mm and a thickness of 1.05 mm. To clean the flux of bremsstrahlung photons from the electrons, a cylindrical Al absorber with a diameter of 100 mm and length of 150 mm was used. The bremsstrahlung γ-flux were calculated using the open certified code GEANT4.9.2 [33] with due regard to the real geometry of the experiment, where the spatial and energy distributions of the electron beam were taken into account.Figure 1. Schematic block diagram of the experiment. The upper part shows the measuring room and the room for accelerator performance control. The lower part shows (from right to left) two sections of the accelerator LUE-40, Ta converter, Al absorber, and bombardment chamber.
The targets made of natural tantalum and molybdenum with a diameter of 8 mm were placed in an aluminum capsule and, using a pneumatic transport system, were transported to the irradiation site and back to the detector. At the end of irradiation, the capsule with the targets was delivered to the measurement room and within 150–200 s, the sample under study was removed from the capsule and placed to measure the induced γ-activity. This made it possible to experimentally obtain data on the yield of the reaction
$^{181}{\rm{Ta}}(\gamma,3{n})^{178{\rm{g}}}{\rm{Ta}}$ , which has a relatively short half-life$ T_{1/2} = 9.31\pm0.03 $ min [1].In the experiments, ten pairs of natural Ta/Mo samples were exposed to radiation at different end-point bremsstrahlung energies
$ E_{\rm{\gamma max}} $ in the range of 35 to 80 MeV. The masses of the Ta and Mo targets were, ~43 mg and ~60 mg, respectively. The time of irradiation$ t_{\rm{irr}} $ and the time of residual activity spectrum measurement$ t_{\rm{meas}} $ were both 30 min. To exemplify, Fig. 2 shows two fragments of the γ-radiation spectrum from the tantalum target in the energy ranges$ 300 \leqslant E_{\gamma} \leqslant 600 $ keV and$ 1200 \leqslant E_{\gamma} \leqslant 1500 $ keV in which the used γ-lines of the 178Ta nucleus are located.Figure 2. (color online) Fragment of the γ-radiation spectrum in the energy ranges of
$300 \leqslant E_{\gamma} \leqslant 600$ keV and$1200 \leqslant E_{\gamma} \leqslant 1500$ keV from the tantalum target of mass 42.928 mg after exposure to the bremsstrahlung γ-flux at$E_{\rm{\gamma max}}$ = 80.7 MeV, with$t_{\rm{irr}}$ = 30 min.For γ-radiation registration, a semiconductor HPGe detector (Canberra GC-2018) was used with resolutions of 1.8 keV and 0.8 keV (FWHM) for the energies
$ E_{\gamma} $ = 1332 keV and 122 keV, respectively. The absolute registration efficiency of the detector was calibrated with a standard set of γ-ray sources 22Na, 60Co, 133Ba, 137Cs, 152Eu, and$ ^{241}{\rm{Am}} $ .To investigate the reactions of interest, the residual activity γ-spectrum of the irradiated target was analyzed, and
$ \triangle A $ – the number of counts of γ-quanta in the full absorption peak were determined for the γ-lines corresponding to the nuclei-products$ ^{178{\rm{g}}} $ Ta and$ ^{178{\rm{m}}} $ Ta. Referring to the data from Ref. [1], Table 1 lists the parameters of both the reactions under study and the monitoring reaction, viz., the energy$ E_{\gamma} $ and intensity$ I_{\gamma} $ of the γ-lines in use.Nuclear reaction $E_{\rm{th}}$ /MeV a)$J^\pi$ of nucleus-product$T_{1/2}$ $E_{\gamma}$ /keV$I_{\gamma}$ (%)$^{181}{\rm{Ta} }(\gamma,3{n})^{178{\rm{g} } }{\rm{Ta} }$ 22.05 $1^+$ 9.31 (3) min 1350.68 (3) 1.18 (3) $^{181}{\rm{Ta} }(\gamma,{3n })^{ {\rm{178m} } }{\rm{Ta} }$ 22.35 $(7)^-$ 2.36 (8) h 426.383 (6) 97.0 (13) $^{100}{\rm{Mo} }(\gamma,{n})^{99}{\rm{Mo} }$ 8.29 $1/2^+$ 65.94 (1) h 739.50 (2) 12.13 (12) a) The values of the reaction thresholds $E_{\rm{th}}$ are obtained from the TALYS1.95 code.Table 1. Spectroscopic data [1] on the nuclei-products from the reactions
$^{181}{\rm{Ta}}(\gamma,3{n})^{178\rm{m,g}}{\rm{Ta}}$ and the monitoring reaction$^{100}{\rm{Mo}}(\gamma,{n})^{99}{\rm{Mo}}$ .During the experiment, as the real conditions may deviate from the conditions used in the calculations, it can lead to an unexpected deviation of the bremsstrahlung flux on the target. To take this deviation into account, bremsstrahlung γ-flux monitoring by the
$^{100}{{\rm{Mo}}}(\gamma,{n})^{99}{{\rm{Mo}}}$ reaction yield was performed by comparing the experimentally obtained average cross-section values$ \langle{\sigma(E_{\rm{\gamma max}})}\rangle_{\rm{exp}} $ with the computation data$ \langle{\sigma(E_{\rm{\gamma max}})}\rangle_{\rm{th}} $ . The normalization coefficients$k = $ $ \langle{\sigma(E_{\rm{\gamma max}})}\rangle_{\rm{th}}$ /$ \langle{\sigma(E_{\rm{\gamma max}})}\rangle_{\rm{exp}} $ were obtained and varied in a rather narrow range of 1.08 ÷ 1.15. To determine the experimental$ \langle{\sigma(E_{\rm{\gamma max}})}\rangle_{\rm{exp}} $ values, the yield for the γ-line of energy$ E_{\gamma} $ = 739.50 keV and intensity$ I_{\gamma} $ = 12.13% (see Table 1). The average cross-section$ \langle{\sigma(E_{\rm{\gamma max}})}\rangle_{\rm{th}} $ values were computed with the cross-sections$ \sigma(E) $ from the TALYS1.95 code. Details of the monitoring procedure can be found in [29, 34].The Ta converter and Al absorber used in the experiment generate neutrons that can cause the reaction
$^{100}{{\rm{Mo}}}({n},{2n})^{99}{{\rm{Mo}}}$ . The energy neutrons spectrum was calculated along with the fraction of neutrons with energies above the threshold of this reaction, similar to that in [35, 36]. The contribution of the$^{100}{{\rm{Mo}}}(n,2n)^{99}{{\rm{Mo}}}$ reaction to the value of the induced activity of the$ ^{99}{{\rm{Mo}}} $ nucleus has been estimated and it has been shown that this contribution is negligible compared to the contribution of$^{100}{{\rm{Mo}}}(\gamma,{n})^{99}{{\rm{Mo}}}$ .When calculating the values of the average reaction cross-sections, it was assumed that all radioactive isotopes were formed only as a result of the photonuclear reactions at 181Ta, as the concentration of the
$ ^{180{\rm{m}}} $ Ta isomer in a natural mixture of tantalum is negligible (0.012%). The self-absorption of γ-radiation from the reaction products in the target was calculated using the GEANT4.9.2 code, which was accounted for in the calculations.The uncertainty of the measurements of the average cross-sections
$ \langle{\sigma(E_{\rm{\gamma max}})}\rangle $ ,$ \langle{\sigma(E_{\rm{\gamma max}})}\rangle_{{\rm{m}}} $ , and$ \langle{\sigma(E_{\rm{\gamma max}})}\rangle_{{\rm{g}}} $ was determined as a squared sum of the statistical and systematic errors. The statistical error in the observed γ-activity is mainly associated with the statistics calculation for the total absorption peak of the corresponding γ-line and is estimated to be in the range of 2%–10% for$ E_{\gamma} $ = 1350.68 keV and up to 2% for$ E_{\gamma} $ = 426.383 keV. The systematic errors stem from the uncertainties in the 1) irradiation time – 0.25%–0.5%; 2) electron current – 0.5%; 3) γ-radiation detection efficiency – ~2%–2.5%, mainly due to the measuring error of the γ-radiation sources; 4) half-life period$ T_{1/2} $ of the reaction products and the intensity of the analyzed γ-quanta$ I_{\gamma} $ (see Table 1); 5) normalization of the experimental data to the yield of the monitoring reaction$^{100}{{\rm{Mo}}}(\gamma,{n})^{99}{{\rm{Mo}}}$ – 2.5%; and 6) the GEANT4.9.2 computational error for the bremsstrahlung γ-flux – ~1.5%.It should be noted that the systematic error in the
$^{100}{{\rm{Mo}}}(\gamma,{n})^{99}{{\rm{Mo}}}$ reaction yield is associated with three fundamentally unremovable errors, each of which is ~1%: unidentified isotopic composition of natural molybdenum, uncertainty in the intensity of the used γ-line$ I_{\gamma} $ [1], and the statistical error in determining the area under the peak of the normalizing γ-line. In the calculations, we used the value of the isotopic abundance of the$ ^{100}{{\rm{Mo}}} $ nucleus reported in [33], which is 9.63%.Thus, the experimental error of the obtained average cross-sections is within 6%–11%.
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The values of the cross-sections
$ \langle{\sigma(E_{\rm{\gamma max}})}\rangle $ , averaged over the bremsstrahlung flux of the γ-quanta$ W(E,E_{\rm{\gamma max}}) $ from the threshold$ E_{\rm{th}} $ of the reaction under consideration to the boundary energy of the spectrum$ E_{\rm{\gamma max}} $ , were calculated using the cross-sections$ \sigma(E) $ from the TALYS1.95 code [26]. The bremsstrahlung flux-averaged cross-section$ \langle{\sigma(E_{\rm{\gamma max}})}\rangle $ was calculated according to the formula:$ \langle{\sigma(E_{\rm{\gamma max}})}\rangle = \frac {\displaystyle\int_{E_{\rm{th}}}^{E_{\rm{\gamma max}}}\sigma(E)\cdot W(E,E_{\rm{\gamma max}}){\rm d}E} {\displaystyle\int_{E_{\rm{th}}}^{E_{\rm{\gamma max}}}W(E,E_{\rm{\gamma max}}){\rm d}E}. $
(1) These calculated values of the average cross-sections were compared with the experimental values obtained in the work, which were calculated using the formula:
$ \begin{aligned}[b]& \langle{\sigma(E_{\rm{\gamma max}})}\rangle = \\& \frac{\lambda \triangle A}{N_x I_{\gamma} \ \varepsilon \Phi(E_{\rm{\gamma max}}) (1-\exp(-\lambda t_{\rm{irr}}))\exp(-\lambda t_{\rm{cool}})(1-\exp(-\lambda t_{\rm{meas}}))}, \end{aligned} $
(2) λ is the decay constant (
$ {\rm{ln}}2/T_{1/2} $ ), where$ \triangle A $ is the number of counts of γ-quanta in the full absorption peak (for the γ-line of the investigated reaction),$ N_x $ is the number of target atoms,$ I_{\gamma} $ is the intensity of the analyzed γ-quanta,$ \varepsilon $ is the absolute detection efficiency for the analyzed γ-quanta energy,${\rm{\Phi}}(E_{\rm{\gamma max}}) = {\int_{E_{\rm{th}}}^{E_{\rm{\gamma max}}}W(E,E_{\rm{\gamma max}}){\rm d}E}$ is the sum of the bremsstrahlung quanta in the energy range from the reaction threshold$ E_{\rm{th}} $ up to$ E_{\rm{\gamma max}} $ , and$ t_{\rm{irr}} $ ,$ t_{\rm{cool}} $ , and$ t_{\rm{meas}} $ are the irradiation time, cooling time, and measurement time, respectively. For further details, all the calculation procedures required to determine$ \langle{\sigma(E_{\rm{\gamma max}})}\rangle $ are described in [25, 29, 34].If the product nucleus has an isomeric state, the value of the total averaged cross-section
$ \langle{\sigma(E_{\rm{\gamma max}})}\rangle_{\rm{tot}} $ (hereinafter$ \langle{\sigma(E_{\rm{\gamma max}})}\rangle $ ) of the reaction under study is calculated as the sum of$ \langle{\sigma(E_{\rm{\gamma max}})}\rangle_{{\rm{m}}} $ and$ \langle{\sigma(E_{\rm{\gamma max}})}\rangle_{{\rm{g}}} $ , respectively, of the average cross-sections for the population of the isomeric and ground states, each with its reaction threshold$ E_{\rm{th}} $ (see Table 1).The isomeric ratio of the reaction products is defined as the ratio of the cross-section
$ \sigma_{{\rm{m}}}(E) $ of the formation of the nucleus in the metastable (usually high-spin) state to the cross-section$ \sigma_{{\rm{g}}}(E) $ of the nucleus in the ground state. This definition enables estimation of the degree of the population of the metastable state concerning the ground state of the product nucleus.In the case of experiments on the bremsstrahlung beam of γ-quanta, the isomeric ratio is defined as the ratio of the yields or as the ratio of the average cross-sections for the formation of reaction products in the metastable and ground states. The expression for
$ d(E_{\rm{\gamma max}}) $ in terms of the average cross-sections can be written as:$ d(E_{\rm{\gamma max}}) = {\langle{\sigma(E_{\rm{\gamma max}})}\rangle_{{\rm{m}}}} / {\langle{\sigma(E_{\rm{\gamma max}})}\rangle_{{\rm{g}}}}. $
(3)
Isomeric ratio of the 181Ta(γ, 3n)178m,gTa reaction products at energy Eγmax up to 95 MeV
- Received Date: 2027-07-14
- Available Online: 2022-01-15
Abstract: The photoneutron reaction