Measurement of 92Mo(n,α)89Zr and 97Mo(n,p)97Nb reactions at the neutron energy 13.52 MeV with covariance analysis (original) (raw)
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Journal of Radioanalytical and Nuclear Chemistry, 2020
The 115 In(n,2n) 114m In and 197 Au(n,2n) 196 Au reaction cross sections have been measured relative to the 27 Al(n,α) 24 Na monitor reaction at the two different incident neutron energies of 13.520 ± 0.005 MeV and 14.54 ± 0.24 MeV. The neutrons from the D-T fusion reaction at the Purnima neutron generator were used for activation followed by off-line γ-ray spectrometry. The uncertainty propagation and correlation of measured reaction cross sections were estimated using covariance analysis through considering the partial uncertainties in different attributes. The measured reaction cross sections from the present work have been compared with the literature data from EXFOR compilation, ENDF data of various libraries and theoretically calculated values from the TALYS-1.9 code. Keywords 115 In(n,2n) 114m In and 197 Au(n,2n) 196 Au reaction cross sections • Activation and off-line γ-ray spectrometry • Covariance analysis • TALYS-1.9 code * Haladhara Naik
Journal of Radioanalytical and Nuclear Chemistry, 2019
The 67 Zn(n,p) 67 Cu, 64 Zn(n,2n) 63 Zn, 89 Y(n,γ) 90m Y and 89 Y(n,2n) 88 Y reaction cross sections relative to the 197 Au(n,2n) 196 Au monitor reaction have been determined at the neutron energy of 14.54 ± 0.002 MeV by using the method of activation and off-line γ-ray spectrometry. The neutron energy used was obtained from the 3 H(d,n) 4 He reaction. The covariance analysis was performed by taking the uncertainties arising in various attributes and the correlations between those attributes. The analyzed results from the present measurement were compared with the literature data and evaluated data of various libraries like ENDF/B-VIII, JEFF-3.3, JENDL-4.0 and ROSFOND-2010 libraries as well as with the calculated values based on TALYS-1.9 code. Keywords 67 Zn(n,p) 67 Cu • 64 Zn(n,2n) 63 Zn, 89 Y(n,γ) 90m Y and 89 Y(n,2n) 88 Y reactions • 3 H(d,n) 4 He reaction neutron • γ-Ray spectrometry • Covariance analysis • TALYS-1.9
Annals of Nuclear Energy, 2005
Activation cross-sections for the (n, n 0 ) reaction were measured by means of the activation method at neutron energies of 3.1 and 2.54 MeV using a pulsed neutron beam. The target nuclei were 79 Br, 90 Zr, 197 Au, and 207 Pb whose half-lives were between 0.8 and 8 s. The value of the 90 Zr(n, n 0 ) 90m Zr reaction was obtained for the first time. In order to confirm the pulsed neutron beam measuring method, the cross-section data of 79 Br and 197 Au were compared with previous data obtained using a pneumatic sample transport system. The results of this comparison were in agreement within the range of experimental error. The d-D neutrons were generated by bombarding a deuterated titanium target with a 350-keV d + -beam at the 80°b eam line of the Fusion Neutronics Source (FNS) at the Japan Atomic Energy Research Institute. In order to obtain reliable activation cross-sections, careful attention was paid to correct 0306-4549/$ -see front matter Ó annals of NUCLEAR ENERGY the efficiency for a volume source, and the self-absorption of gamma rays in irradiated samples. The systematics of the (n, n 0 ) reaction at a neutron energy of 3.0 MeV, which can predict cross-section of (n, n 0 ) reaction with an accuracy of 50%, was proposed for the first time on the basis of our data.
Physical Review C, 2020
The cross section of the 23 Na(n, γ) 24 Na, 41 K(n, p) 41 Ar, 65 Cu(n, p) 65 Ni, and 127 I(n, 2n) 126 I reactions have been measured at 14.92 ± 0.02 MeV neutron energy through neutron activation method followed by off-line γ-ray spectrometry. 27 Al(n, α) 24 Na is used as a reference reaction for the neutron flux normalization. The neutron beam was produced via the 3 H(d, n) fusion reaction. Detailed uncertainty propagation has been performed using the covariance analysis and the measured cross sections are being reported with their uncertainties and correlation matrix. The cross sections measured in the present work are compared with the earlier reported cross sections available in the EXFOR database. Furthermore, theoretical calculations have been performed using the EMPIRE-3.2 and TALYS-1.9 codes with RIPL-3 parametrization, from reaction threshold to 20 MeV. The present experimental cross sections are also compared with the evaluated nuclear data from TENDL-2017, JENDL-4.0, and ENDF/B-VIII.0. In the case of (n, γ) and (n, 2n) reactions, the comparison is also made with the IRDFF-1.05 evaluation.
93Nb(n,2n)92mNb, 93Nb(n,α)90mY and 92Mo(n,p)92mNb reactions at 14.78 MeV and covariance analysis
Journal of Radioanalytical and Nuclear Chemistry, 2019
The cross sections for the 93 Nb(n,2n) 92m Nb, 93 Nb(n,α) 90m Y and the 92 Mo(n,p) 92m Nb reactions have been measured with respect to the 197 Au(n,2n) 196 Au monitor reaction at the incident neutron energy of 14.78 ± 0.19 MeV by employing methods of activation and off-line γ-ray spectrometry. The covariance analysis was carried out by taking into consideration of partial uncertainties in different attributes and correlation among the attributes. The present data have been compared with the literature data available in EXFOR, evaluated data of different libraries and theoretical values based on TALYS-1.8 code. Keywords 93 Nb(n,2n) 92m Nb, 93 Nb(n,α) 90m Y and 92 Mo(n,p) 92m Nb reactions • Cross sections • 3 H(d,n) 4 He reaction neutron • Activation and off line γ-ray spectrometry • Covariance analysis • TALYS-1.8
Annals of Nuclear Energy, 2003
Cross sections were measured at neutron energies from 13.6 to 14.9 MeV for the reaction 97 Mo(n,p) 97m Nb leading to isomer of Niobium-97 isotope. The production of relatively shortlived isomer activity and the spectra accumulation have been carried out by cyclic activation method. Corrections were made for the effects of gamma ray attenuation, random coincidence summing (pulse pileup), dead time, neutron flux fluctuations and scattered low energy neutron contribution. Statistical model calculations for which the pre-equilibrium emission effects are taken into consideration were also performed for the investigated reaction between 13.0 and 15.0 MeV neutron energy range.
Measurement of reaction cross-sections for 89 Y at average neutron energies of 7.24-24.83 MeV
EPJ Web of Conferences, 2015
We measured neutron-induced reaction cross-sections for 89 Y(n,γ) 90m Y and 89 Y(n,α) 86 Rb reactions with the average neutron energy region from 7.45 to 24.83 MeV by an activation and off-line γ-ray spectrometric technique using the MC-50 Cyclotron at Korea Institute of Radiological and Medical Sciences. The neutron-induced reaction cross-sections of 89 Y as a function of neutron energy were taken from the TENDL-2013 library. The flux-weighted average cross-sections for 89 Y(n,γ) 90m Y and 89 Y(n,α) 86 Rb reactions were calculated from the TENDL-2013 values based on mono-energetic neutron and by using the neutron energy spectrum from MCNPX 2.6.0 code. The present results are compared with the flux-weighted values of TENDL-2013 and are found to be in good agreement
Annals of Nuclear Energy, 2012
Off-line c-ray spectrometric technique 7 Li(p, n) 7 Be reaction Neutron energies of 8.04 ± 0.3 MeV and 11.9 ± 0.35 MeV Talys 1.2 computer code a b s t r a c t The 232 Th(n, c) 233 Th and 232 Th(n, 2n) 231 Th reaction cross-sections have been determined for the first time at average neutron energies of 8.04 ± 0.30 MeV and 11.90 ± 0.35 MeV using activation and off-line c-ray spectrometric technique. The neutron beam was generated using 7 Li(p, n) reaction. The experimentally determined cross-sections were compared with the evaluated nuclear data libraries of ENDF/B-VII and JENDL 4.0 and are found to be in good agreement. The 232 Th(n, c) 233 Th and 232 Th(n, 2n) 231 Th reaction cross-sections were also calculated theoretically using TALYS 1.2 computer code and compared with the experimental data.
Pramana, 2012
The 232 Th(n, γ ) reaction cross-section at average neutron energies of 13.5, 15.5 and 17.28 MeV from the 7 Li( p, n) reaction has been determined for the first time using activation and off-line γ -ray spectrometric technique. The 232 Th(n, 2n) cross-section at 17.28 MeV neutron energy has also been determined using the same technique. The experimentally determined 232 Th(n, γ ) and 232 Th(n, 2n) reaction cross-sections from the present work were compared with the evaluated data of ENDF/BVII and JENDL-4.0 and were found to be in good agreement. The present data, along with literature data in a wide range of neutron energies, were interpreted in terms of competition between 232 Th(n, γ ), (n, f ), (n, n f ) and (n, xn) reaction channels. The 232 Th(n, γ ) and 232 Th(n, 2n) reaction cross-sections were also calculated theoretically using the TALYS 1.2 computer code and were found to be in good agreement with the experimental data from the present work but were slightly higher than the literature data at lower neutron energies.
Measurement of Th232(n,γ) reaction cross sections in the neutron energy range of 11–19 MeV
Physical Review C, 2018
The cross sections for the 232 Th(n, γ) reaction have been measured in the neutron energy range of 11-19 MeV by using activation and offline γ-ray spectrometric techniques. The neutrons of desired energy were obtained by the 7 Li(p, n) reaction using a proton beam of 13-21 MeV from the 14UD BARC-TIFR Pelletron facility at Mumbai, India. The 232 Th(n, γ) reaction cross sections were calculated using the computer code TALYS-1.8. The uncertainties in the measurement have been studied using covariance analysis of the experimental data. The results from the present work have been compared with the evaluated data of ENDF/B-VII.1 and JENDL-4.0 as well as the theoretically calculated values based on TALYS-1.8, and were found to be in good agreement. The outcome of the present work is important for the development of future fast reactors and accelerator driven subcritical systems (ADSs).