Physico-chemical Analysis of beeswax procured from Mumbai market, Western Ghats (Natural Habitat)

Beeswax is the substance that is obtained from the structure of a honey comb. The bees secrete wax to build the honey combs to store honey. It has rich hydrophobic property, the beeswax is in fact present within cosmetics and body products. Also, beeswax is used in food industry. Beeswax is a complex mixture of hydrocarbons, free fatty acid, esters of fatty acid. Beeswax plays an important role in Ayurvedic medicine, the traditional medicine name with Madhushistha (Beewax). The Madhushistha is used for the care of wound from abrasion or even from burns with topical application. Some references in Ayurvedic granth highlight the use of Madhushistha in combination with other herbal and mineral mixture, like Sikta Taila, Mruddaharshringa, Jatyadi Taila, etc. Beeswax is mainly of two types, natural beeswax and processed beeswax. Natural beeswax is clarified further heating in water with petroleum waxes. Because of high demand and shortage in market, adulteration of beeswax with cheaper materials are common like animal fat, plant oil and petroleum spirits (Paraffin wax). Hence authenticity of beeswax is major concern and that can be determined by using physico-chemical parameters such as- organoleptic test, solubility, Melting point, Spacific gravity, Refractive index, Acid value, Ester value, Saponification value, volatile matter. With this justification the present study is expected to determine the quality status of four different beeswax samples procured from Mumbai market, western ghats (Natural habitat). The physico-chemical analysis revealed that volatile matter is detected in market sample (2) whereas market sample (1) shows higher melting point as compare to beeswax collected from the Natural habitat. Market sample (1,2) of beeswax shows slight adulteration hence natural habitat samples (1,2) of beeswax should be used in medicine preparation

Measurement of 67Zn(n,p) 67Cu, 64Zn(n,2n) 63Zn, 89Y(n,&gamma,) 90mY and 89Y(n,2n) 88Y Reaction Cross Sections at the Neutron Energy of 14.54 MeV with Covariance Analysis

The 67Zn(n,p)67Cu, 64Zn(n,2n)63Zn, 89Y(n,&gamma,)90mY and 89Y(n,2n)88Y reaction cross sections relative to the 197Au(n,2n)196Au monitor reaction have been determined at the neutron energy of 14.54 ,± ,0.002 MeV by using the method of activation and off-line &gamma,-ray spectrometry. The neutron energy used was obtained from the 3H(d,n)4He 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

Measurement of 67Zn(n,p) 67Cu, 64Zn(n,2n) 63Zn, 89Y(n,&gamma,) 90mY and 89Y(n,2n) 88Y Reaction Cross Sections at the Neutron Energy of 14.54 MeV with Covariance Analysis

The 67Zn(n,p)67Cu, 64Zn(n,2n)63Zn, 89Y(n,&gamma,)90mY and 89Y(n,2n)88Y reaction cross sections relative to the 197Au(n,2n)196Au monitor reaction have been determined at the neutron energy of 14.54 ,± ,0.002 MeV by using the method of activation and off-line &gamma,-ray spectrometry. The neutron energy used was obtained from the 3H(d,n)4He 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

93Nb(n,2n) 92mNb, 93Nb(n,α) 90mY and 92Mo(n,p) 92mNb Reactions at 14.78 MeV and Covariance Analysis

The cross sections for the 93Nb(n,2n)92mNb, 93Nb(n,α)90mY and the 92Mo(n,p)92mNb reactions have been measured with respect to the 197Au(n,2n)196Au 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

Synthesis and characterization of multifunctional ZnBr2/PVA polymer dielectrics

Different weight percentage of ZnBr2 doped poly(vinyl alcohol) (PVA) free standing composite films were prepared using solution casting method. These films were characterized for analyzing structural, dielectric, electrochemical properties. This paper mainly focused to understand the contribution of physical phenomenon on conductivity in terms of dielectric parameters. FTIR spectrum confirms the interaction between ZnBr2 and PVA. Pseudo-capacitive behavior observed from cyclic voltammograms. Dielectric properties of the composites follow non-Debye type behavior. The conducting phenomenon occurs due to hopping of ions between coordination sites present in the composite and the segmental relaxation of polymer chain

Measurement of

The $$^{96}\rm{Zr}(n,\gamma)^{97}Zr$$ reaction cross sections relative to $$^{197}\rm{Au}(n,\gamma)^{198}Au$$ monitor reaction with the neutron energies of 0.61 and 1.05 MeV from the 7Li(p,n)7Be reaction have been measured for the first time by using the activation and off-line $\gamma$-ray spectrometric technique. The error analysis of the experimental data was done by considering the partial uncertainties in various attributes and the correlations between those attributes were reported through covariance analysis. The present experimental cross sections have been compared with the theoretical prediction by TALYS-1.8 using the back-shifted Fermi gas model and Brink-Axel Lorentzian $\gamma$-ray strength functions. The TALYS-1.8 calculations well predicted the present experimental cross sections at both neutron energies. The spectrum averaged neutron capture cross sections of 96Zr obtained in the present work have also been compared with the evaluated cross sections from ENDF/B-VIII.0, JENDL-4, JEFF-3.3, CENDL-3.1 and TENDL-2015 libraries. They are found to be in close agreement with the TENDL-2015 and CENDL-3.1 libraries at the neutron energies of 0.61 and 1.05 MeV

Measurement of 14.54 MeV Neutron Induced Reaction Cross Sections of Cr and Mn with Covariance Analysis

The 50Cr(n,2n)49Cr, 52Cr(n,2n)51Cr, 52Cr(n,p)52V, 55Mn(n,2n)54Mn, 55Mn(n,α)52V and 55Mn(n,γ)56Mn reaction cross sections at the neutron energy of 14.54 ± 0.24 MeV were measured by using activation method along with off-line γ-ray spectrometry. The 27Al(n,p)27Mg monitor reaction was used for the 52Cr(n,p)52V and 55Mn(n,α)52V reactions, whereas the 197Au(n,γ)198Au monitor reaction for the 55Mn(n,γ)56Mn reaction. The 27Al(n,α)24Na monitor reaction was used for other three reactions. The neutron beam was generated from the T(d,n)4He reaction using the Purnima neutron generator at BARC, Mumbai. The covariance analysis for the uncertainties of reaction cross sections was performed by considering the correlations between different attributes. The present results were compared with the literature data, evaluated data of ENDF, ROSFOND, CENDL, JENDL and JEFF libraries as well as with the theoretical values based on TALYS-1.9 calculation

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