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A. Gandhi

Publications and source records attributed to A. Gandhi.

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Neutron capture measurements for s-process nucleosynthesis; A review about CERN n_TOF developments and contributions

This article presents a review about the main CERN n\_TOF contributions to the field of neutron-capture experiments of interest for $s$-process nucleosynthesis studies over the last 25 years, with special focus on the measurement of radioactive isotopes. A few recent capture experiments on stable isotopes of astrophysical interest are also discussed. Results on $s$-process branching nuclei are appropriate to illustrate how advances in detection systems and upgrades in the facility have enabled increasingly challenging experiments and, as a consequence, have led to a better understanding and modeling of the $s$-process mechanism of nucleosynthesis. New endeavors combining radioactive-ion beams from ISOLDE for the production of radioisotopically pure samples for activation experiments at the new NEAR facility at n\_TOF are briefly discussed. On the basis of these new exciting results, also current limitations of state-of-the-art TOF and activation techniques will be depicted, thereby showing the pressing need for further upgrades and enhancements on both facilities and detection systems. A brief account of the potential technique based on inverse kinematics for direct neutron-capture measurements is also presented.

nucl-ex

Uncertainty propagation and covariance analysis of 181Ta(n,γ)182Ta nuclear reaction

The neutron capture cross-section for the $^{181}$Ta(n,$γ$)$^{182}$Ta reaction has been experimentally measured at the neutron energies 0.53 and 1.05 MeV using off-line $γ$-ray spectrometry. $^{115}$In(n,n'$γ$)$^{115m}$In is used as a reference monitor reaction cross-section. The neutron was produced via the $^{7}$Li(p,n)$^{7}$Be reaction. The present study measures the cross-sections with their uncertainties and correlation matrix. The self-attenuation process, $γ$-ray correction factor, and low background neutron energy contribution have been calculated. The measured neutron spectrum averaged cross-sections of $^{181}$Ta(n,$γ$)$^{182}$Ta are discussed and compared with the existing data from the EXFOR database and also with the ENDF/B-VIII.0, TENDL-2019, JENDL-5, JEFF-3.3 evaluated data libraries.

nucl-ex

Measurement of alpha-induced reaction cross-sections for $^{nat}$Zn with detailed covariance analysis

The production cross-section of $^{68}$Ge, $^{69}$Ge, $^{65}$Zn and $^{67}$Ga radioisotopes from alpha-induced nuclear reaction with $^{nat}$Zn have been measured using the stacked foil activation technique followed by the off-line $γ$-ray spectroscopy in the incident alpha energy range 14-37 MeV. The obtained nuclear reaction cross-sections are compared with previous experimental data available in the EXFOR data library, evaluated nuclear data from TENDL-2019 and theoretical results, calculated using TALYS nuclear reaction code. We have also performed the detailed uncertainty analysis for these nuclear reactions and their respective correlation metrics are presented. Since $α$-induced reactions are important in nuclear medicine and developing the nuclear reaction codes so needful corrections related to the coincidence summing factor and the geometric factor have been considered during the data analysis in the present study.

nucl-ex

Statistical analysis of proton induced reactions to generate recommended data for the production of medical radio-isotopes

Radio-isotopes produced via proton induced reaction holds special significance regarding nuclear medicine, astrophysical p-process, theragnostic and diagnostic processes. $^{76}$Br, $^{80m}$Br and $^{61}$Cu are positron emitter and they are useful in the functional studies via Positron Emission Tomography (PET), whereas $^{77}$Br bears the potential for the application in Single Photon Emission Computed Tomography (SPECT) which involves electron capture process. PET and SPECT have been in high application in medical physics, diagnostics, therapy and nuclear medicine. $^{99m}$Tc and $^{64}$Cu are two popular radionuclide which play important role in nuclear medicine, currently being used in bio-medical physics, bone scan, modern imaging, blood pool leveling, oncology and diagnosis of copper related diseases. This paper focus on the generation of recommended nuclear reaction cross sections for the production of some useful medical radio-isotopes using the experimental datasets obtained from EXFOR database and simulated datasets from nuclear reaction model codes TALYS-1.95 and EMPIRE-3.1.1. 95\% confidence interval has been implemented to ensure confidence and precision.

nucl-th

Measurement of alpha induced reaction cross-sections on $^{nat}$Mo with detailed covariance analysis

In the present study we have measured the excitation functions for the nuclear reactions $^{100}$Mo($α$,n)$^{103}$Ru, $^{nat}$Mo($α$,x)$^{97}$Ru, $^{nat}$Mo($α$,x)$^{95}$Ru, $^{nat}$Mo($α$,x)$^{96g}$Tc, $^{nat}$Mo($α$,x)$^{95g}$Tc and $^{nat}$Mo($α$,x)$^{94g}$Tc in the energy range 11-32 MeV. We have used the stacked foil activation technique followed by off-line gamma ray spectroscopy technique to measure the excitation functions. In this study we have also documented detailed uncertainty analysis for these nuclear reactions and their corresponding covariance matrix are also presented. The excitation functions are compared with the available experimental data from EXFOR data library and the theoretical prediction from TALYS nuclear reaction code. The present measurements are found to be consistent with the available experimental data.

nucl-ex

Measurement of the response of a liquid scintillation detector to monoenergetic electrons and neutrons

The response of the liquid scintillator (EJ-301 equivalent to NE-213) to the monoenergetic electrons produced in Compton scattered $γ$-ray tagging has been carried out for various radioactive $γ$-ray sources. The measured electron response is found to be linear up to $\sim$4~MeVee and the resolution of the liquid scintillator at 1~MeVee is observed to be $\sim$~11\%. The pulse shape discrimination and pulse height response of the liquid scintillator for neutrons has been measured using $^7$Li(p,n$_1$)$^7$Be*(0.429 MeV) reaction. Non linear response to mono-energetic neutrons for the liquid scintillator is observed at E$_n$=5.3, 9.0 and 12.7 MeV. The measured response of the liquid scintillator for electrons and neutrons have been compared with Geant4 simulation.

physics.ins-det