Browsing by Author "B. Lalremruata"

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Measurement of (n,γ), (n,p), and (n,2n) reaction cross sections for sodium, potassium, copper, and iodine at neutron energy 14.92±0.02 MeV with covariance analysis MEASUREMENT of (N,γ), (N,P), and (n,2n) REACTION ... A. GANDHI et al.
(American Physical Society, 2020) A. Gandhi; Aman Sharma; A. Kumar; Rebecca Pachuau; B. Lalremruata; S.V. Suryanarayana; L.S. Danu; Tarun Patel; Saroj Bishnoi; B.K. Nayak
The cross section of the Na23(n,γ)Na24, K41(n,p)Ar41, Cu65(n,p)Ni65, and I127(n,2n)I126 reactions have been measured at 14.92±0.02 MeV neutron energy through neutron activation method followed by off-line γ-ray spectrometry. Al27(n,α)Na24 is used as a reference reaction for the neutron flux normalization. The neutron beam was produced via the H3(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. © 2020 American Physical Society.
Measurement of neutron capture cross section on 71Ga at 2.15 and 3.19 MeV and uncertainty propagation and covariance analysis
(Institute of Physics, 2023) Rebecca Pachuau; A. Gandhi; Namrata Singh; A. Kumar; Mayur Mehta; S.V. Suryanarayana; L.S. Danu; B.K. Nayak; B. Lalremruata
The cross section values of the Ga( ) Ga reaction are measured, which are mb and mb at 2.15 and 3.19 MeV, respectively. The detailed uncertainty propagation and covariance analysis are also given. The Li( ) Be reaction was used to generate the neutrons, and the neutron flux was normalized using the In( ) In monitor reaction. The measured cross section data are compared with the data available in the EXFOR database, the data obtained using nuclear reaction model codes EMPIRE-3.2 and TALYS-1.95, and also the evaluated nuclear data from ENDF/B-VIII.0 and JEFF-3.1/A. The comparison shows that our result at 3.19 MeV is in good agreement with those of EMPIRE-3.2 and JEFF-3.1/A. Since there are no other measurements available at 3.19 MeV, our data could not be compared with literature data at 3.19 MeV, but they are consistent with the cross section values available at and MeV. Our result at 2.15 MeV is slightly higher than the literature value available in EXFOR, evaluated value, and theoretically predicted result. © 2023 Chinese Physical Society and the Institute of High Energy Physics of the Chinese Academy of Sciences and the Institute of Modern Physics of the Chinese Academy of Sciences and IOP Publishing Ltd.
Neutron capture reaction cross section measurement for iodine nucleus with detailed uncertainty quantification
(Springer Science and Business Media Deutschland GmbH, 2021) A. Gandhi; Aman Sharma; Rebecca Pachuau; Namrata Singh; Prashant N. Patil; Mayur Mehta; L.S. Danu; S.V. Suryanarayana; B.K. Nayak; B. Lalremruata; A. Kumar
The neutron activation cross section for 127I(n,γ)128I reaction has been experimentally measured with respect to the 115In(n,inl)115Inm reference monitor reaction cross section in the neutron spectrum average energy range 0.60- - 2.51 MeV. The neutrons were produced through 7Li(p,n)7Be reaction, and γ-ray spectra of the residue product were measured offline with the precalibrated lead-shielded HPGe detector. The very first time the covariance analysis was done to quantify the measured cross section uncertainties and the correlation coefficients between the different neutron energy cross sections for iodine nucleus. The needful corrections related to the γ-ray self-attenuation process, γ-ray true coincidence summing effect and the low background neutron energy contributions were considered in the present measurement. Theoretical calculations were done using the standard nuclear reaction model codes TALYS-1.9 and EMPIRE-3.2 to obtain the 127I(n,γ)128I reaction cross section. The measured cross sections were compared with the experimental data available in the EXFOR database, theoretical predicted results, and ENDF/B-VIII.0, JEFF-3.1/A, TENDL-2019, and JENDL-4.0 evaluated nuclear data. © 2021, The Author(s), under exclusive licence to Società Italiana di Fisica and Springer-Verlag GmbH Germany, part of Springer Nature.
Neutron induced cross section measurements on gallium isotopes at neutron energy 14.90 ± 0.01 MeV and covariance analysis
(Elsevier B.V., 2019) Rebecca Pachuau; B. Lalremruata; A. Gandhi; S.V. Suryanarayana; B.K. Nayak; A. Kumar; L.S. Danu
The cross sections of the 69Ga(n,p)69Znm, 69Ga(n,2n)68Ga, 71Ga(n,p)71Znm, 71Ga(n,n′α)67Cu and 71Ga(n,2n)70Ga reactions had been measured at 14.90±0.01MeV neutron energy with the 27Al(n,α)24Na as monitor reaction using Neutron Activation Technique. The data analysis was carried out using the latest decay data. Detail uncertainty propagation had been performed and the measured cross sections are reported with their uncertainties and correlation coefficients. The cross sections newly measured in the present work are compared with the earlier reported cross sections available in the EXFOR Database. The measured cross sections reported by various authors had also been studied and discussed in detail. Theoretical calculations had been performed from reaction threshold to 20 MeV and compared along with the evaluated files from ENDF/B-VIII.0 and JENDL-4.0. © 2019 Elsevier B.V.
Neutron radiative capture cross section for sodium with covariance analysis
(Springer Science and Business Media Deutschland GmbH, 2021) A. Gandhi; Aman Sharma; Rebecca Pachuau; B. Lalremruata; Mayur Mehta; Prashant N. Patil; S.V. Suryanarayana; L.S. Danu; B.K. Nayak; A. Kumar
The neutron radiative capture cross sections measurement has been carried out for the 23Na nucleus in the neutron energy region from 0.6 to 3.2 MeV using the neutron activation technique followed by off-line γ-ray spectrometry. The measurement was made relative to the 115In(n,n′ γ)115In m reference monitor reaction cross section. The neutrons were produced via the 7Li(p,n)7Be reaction. Detailed uncertainty propagation has been performed using the covariance analysis, and the measured cross sections are being reported with their uncertainties, covariance, and correlation matrix. The necessary corrections have been made for the low background neutron energy contribution, γ-ray true coincidence summing, and self-attenuation process. The obtained neutron spectrum averaged cross sections of 23Na(n,γ)24Na are discussed and compared with the existing cross sections data retrieved from the EXFOR database. EMPIRE-3.2 and TALYS-1.9 calculations were performed in order to determine the radiative capture cross section in this energy region. The present results are also compared with the evaluated nuclear data from ENDF/B-VIII.0, TENDL-2019, IRDFF-1.05, JENDL-4.0, and JEFF-3.3. The obtained cross section results are in good agreement with existing experimental data, evaluated libraries, and reaction models for the highest energy points (2.11 and 3.13 MeV), while the lowest-energy point at 0.61 MeV underestimates them. © 2021, Società Italiana di Fisica and Springer-Verlag GmbH Germany, part of Springer Nature.
Study of the uncertainty quantification of the 121Sb(n,γ)122Sb reaction
(Springer Science and Business Media Deutschland GmbH, 2025) Namrata Singh; Mahesh Choudhary; A. Gandhi; Mahima Upadhyay; Ratankumar K. Singh; Akash Hingu; Gaurav P. Mishra; Sukanya De; Laxman Singh Danu; Ajay Vinod Kumar; Renju G. Thomas; Saurav Sood; Sajin Prasad; B. Lalremruata; K. Katovsky; A. Sameer Ruban Kumar
The reaction cross-sections for the 121Sb(n,γ)122Sb reaction were determined at 1.66, 2.65, and 3.05 MeV. The experiment was conducted using the neutron activation technique followed by the offline γ-ray spectrometry. The neutrons were generated using the 7Li(p,n)7Be reaction, and the reaction cross-section for 121Sb(n,γ)122Sb was measured with respect to the 115In(n,n′γ)115Inm monitor reaction cross-section. Wood–Saxon phenomenological optical model potentials (OMP) were used to calculate the uncertainties of the theoretical calculation for the 121Sb(n,γ)122Sb reaction cross-section. The measured reaction cross-section data are compared to the existing data available in the EXFOR database. Additionally, the data are compared to the evaluated data from ENDF/B-VIII.0 and JEFF-3.1/A. TALYS-1.96 nuclear code is used for the theoretical calculations. The measured cross-sections are given along with their uncertainties and covariance matrices. In this work, the theoretical cross-section uncertainties have been estimated using the uncertainties in the level density and optical model parameters. © The Author(s), under exclusive licence to Società Italiana di Fisica and Springer-Verlag GmbH Germany, part of Springer Nature 2025.
Validation of neutron capture cross section on 68Zn in the vicinity of the inelastic scattering threshold
(Springer, 2025) Monika; Sumit Bamal; Priyam Rabha; A. Gandhi; Samuel Lawitlang; B. Lalremruata; Ajay Vinod Kumar; Rajeev Sampath Kumar; Laxman Singh Danu; Satyaranjan S. Santra; Bishnupriya K. Nayak; Rebecca Pachuau
To investigate the energy dependence of the neutron capture cross section on 68Zn close to the inelastic scattering threshold, we measured the 68Zn(n,γ)69Znm reaction cross section at 1.12 ± 0.11, 1.40 ± 0.11, 1.62 ± 0.10 and 2.42 ± 0.09 MeV using the 7Li(p,n)7Be reaction as neutron source. The spectrum averaged neutron energy was computed using the neutron energy spectrum code EPEN and the neutron flux was normalized using the 115In(n,n’)115Inm monitor reaction. The data analysis was carried out using the latest decay data. Necessary corrections have been made for the low energy background neutron contribution and γ-ray self-attenuation. After performing detailed uncertainty propagation, the newly measured cross sections are compared to previously published data found in the EXFOR database as well as to theoretical model predictions using TALYS-2.0 with different level density models and γ-ray strength functions, and also with the most recent nuclear data evaluations, JENDL-5, ENDF/B-VIII.1, and JEFF-4.0. The present work significantly reduces the uncertainty to 6% compared to previously reported values ranging from 11% to 19%. © The Author(s), under exclusive licence to Società Italiana di Fisica and Springer-Verlag GmbH Germany, part of Springer Nature 2025.