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

58Ni(n,p)58Co and 58Ni(n,2n)57Ni reactions at the neutron energy of 14.54 MeV with covariance analysis

241-245The 58Ni(n,p)58Co and 58Ni(n,2n)57Ni reactions cross sections have been estimated relative to 197Au(n,2n)196Au monitor reaction at the incident neutron energy of 14.54±0.0024 MeV from the D-T fusion nuclear reaction using Purnima neutron generator carried through methods of activation and off-line γ-ray spectrometry. The uncertainty propagation and correlation for measured cross sections have been estimated using covariance analysis through considering the partial uncertainties in different attributes. The present measured reaction cross sections data have been analyzed by comparing with the literature data, with various libraries of evaluated data, like ENDF/B-VIII.0, JEFF-3.3, JENDL/AD-2017, ROSFOND-2010 and TALYS-1.9 theoretical calculations

58Ni(n,p)58Co and 58Ni(n,2n)57Ni reactions at the neutron energy of 14.54 MeV with covariance analysis

The 58Ni(n,p)58Co and 58Ni(n,2n)57Ni reactions cross sections have been estimated relative to 197Au(n,2n)196Au monitor reaction at the incident neutron energy of 14.54±0.0024 MeV from the D-T fusion nuclear reaction using Purnima neutron generator carried through methods of activation and off-line γ-ray spectrometry. The uncertainty propagation and correlation for measured cross sections have been estimated using covariance analysis through considering the partial uncertainties in different attributes. The present measured reaction cross sections data have been analyzed by comparing with the literature data, with various libraries of evaluated data, like ENDF/B-VIII.0, JEFF-3.3, JENDL/AD-2017, ROSFOND-2010 and TALYS-1.9 theoretical calculations

A tool for calculation of 7Li(p,n)7Be neutron source spectra below the three-body break-up reaction threshold

We developed a new deterministic neutron source spectrum code EPEN - Energy of Proton Energy of Neutron - for a given lithium target thickness, sample angular coverage and proton energy from the reaction threshold to the three-body break-up threshold. The angular differential cross sections of the 7Li(p,n0)7Be and 7Li(p,n1)7Be reactions evaluated by Liskien and Paulsen were adopted above 1.95 MeV while the functional form suggested by Macklin and Gibbons was adopted for the 7Li(p,n0)7Be reaction cross section near threshold. The spectra obtained by EPEN are validated by the experimental spectra and also compared with the spectra predicted by two Monte Carlo codes, SimLiT and PINO. The results of comparison are discussed in detail

A tool for calculation of

We developed a new deterministic neutron source spectrum code EPEN - Energy of Proton Energy of Neutron - for a given lithium target thickness, sample angular coverage and proton energy from the reaction threshold to the three-body break-up threshold. The angular differential cross sections of the 7Li(p,n0)7Be and 7Li(p,n1)7Be reactions evaluated by Liskien and Paulsen were adopted above 1.95 MeV while the functional form suggested by Macklin and Gibbons was adopted for the 7Li(p,n0)7Be reaction cross section near threshold. The spectra obtained by EPEN are validated by the experimental spectra and also compared with the spectra predicted by two Monte Carlo codes, SimLiT and PINO. The results of comparison are discussed in detail

Neutron radiative capture cross section for sodium with covariance analysis

The neutron radiative capture cross sections measurement has been carried out for the $$^{23}$$Na nucleus in the neutron energy region from 0.6 to 3.2 MeV using the neutron activation technique followed by off-line $$\gamma$$-ray spectrometry. The measurement was made relative to the $$^{115}$$In(n,n$$\prime$$$$\gamma$$)$$^{115}\hbox {In}^{m}$$ reference monitor reaction cross section. The neutrons were produced via the $$^{7}$$Li(p,n)$$^{7}$$Be 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, $$\gamma$$-ray true coincidence summing, and self-attenuation process. The obtained neutron spectrum averaged cross sections of $$^{23}$$Na(n,$$\gamma$$)$$^{24}$$Na 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

Measurement of 14.54 ± 0.24 MeV Neutron Activation Reaction Cross Sections of 93Nb, natMo with Covariance Analysis

The 93Nb(n,α)90mY, 93Nb(n,2n)92mNb and 92Mo(n,p)92mNb reaction cross sections have been measured relative to the 197Au(n,2n)196Au monitor reaction at the neutron energy of 14.54 ± 0.24 MeV. The neutrons were generated from the T(d,n)4He reaction using Purnima neutron generator. The experiment was done by using the method of activation in combination with an off-line γ\documentclass[12pt]{minimal}\usepackage{amsmath}\usepackage{wasysym}\usepackage{amsfonts}\usepackage{amssymb}\usepackage{amsbsy}\usepackage{mathrsfs}\usepackage{upgreek}\setlength{\oddsidemargin}{-69pt}\begin{document}$$\gamma$$\end{document}-ray spectrometry technique. The uncertainties and correlations for the reaction cross sections were estimated with the use of covariance analysis by considering the partial uncertainties in individual attributes. The measured reaction cross sections have been analyzed by comparing with the data available in EXFOR compilation, various files of evaluated data and theoretically calculated values from TALYS-1.9

Erratum to: Fast-neutron induced reaction cross section measurement of tin with dual monitor foils and covariance analysis

A Correction to this paper has been published: 10.1140/epja/s10050-021-00578-

Fast-neutron induced reaction cross section measurement of tin with dual monitor foils and covariance analysis

The fast-neutron induced elemental cross sections have been measured relative to the $$^{197}$$Au(n,2n)$$^{196}$$Au and $$^{27}$$Al(n,$$\alpha$$)$$^{24}$$Na monitor cross sections at 14.5 ± 0.2 MeV by using a natural Sn sample and the activation technique for production of $$^{111}$$Sn, $$^{117}$$Sn$$^m$$, $$^{123}$$Sn$$^m$$, $$^{111}$$In (cumulative), $$^{116}$$In$$^{m1+m2}$$, $$^{117}$$In$$^m$$, $$^{117}$$In$$^g$$ (cumulative), and $$^{118}$$In$$^{m1+m2}$$. The off-diagonal weighted mean of the elemental cross sections were determined by constructing the covariance between the cross sections obtained with the two monitor cross sections. From the measured elemental cross sections, the respective isotopic cross sections were also determined for the $$^{112}$$Sn(n,2n)$$^{111}$$Sn, $$^{124}$$Sn(n,2n)$$^{123}$$Sn$$^{m}$$, $$^{112}$$Sn(n,x)$$^{111}$$In and $$^{118}$$Sn(n,p)$$^{118}$$In$$^{m1+m2}$$ reactions. The comparison of the measured elemental and isotopic cross sections with those in the EXFOR, JEFF-3.1/A, JENDL/AD-2017 and TENDL-2019 libraries as well as those predicted by TALYS-1.9 is discussed