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Background: Perinatal asphyxia is one of the major causes of neonatal morbidity & mortality. Asphyxia can damage almost every organ of neonate. Our purpose was to determine the correlation of cord blood pH with birth asphyxia & early neonatal outcome. Subjects and Methods: A prospective study was conducted over a period of one year at STH Haldwani. We enrolled 108 term neonates with signs of fetal distress, thick MSL, non-reassuring NST & there were subjected for estimation of umbilical cord blood pH, APGAR score, outcome looked were resuscitation needed, NICU admission, delay in feed & encephalopathy (sarnat & sarnat stage). Results: In our study, cord blood pH had significant correlation with perinatal asphyxia(R=-0.926). Area under ROC curved showed that mean pH

BACKGROUND Megaloblastic Anaemia is a common disease caused by nutritional deficiency and is associated with other nutritional deficiencies; but the exact prevalence of megaloblastic anaemia is still not known. This study was conducted to evaluate its incidence and causes in a tertiary care hospital of Uttarakhand. METHODS This is a retrospective study done at Government Medical College and Susheela Tiwari Memorial Hospital, Haldwani, a tertiary referral center of Kumau region between February 2017 to January 2019 and all cases of moderate to severe anaemia were enrolled for study. Among 150 cases of nutritional anaemia, 25 children (age ranges from 5 months to 15 year) were taken from the records of the hospital. Then we prepared the data with age, gender, nutritional history, signs symptoms, socioeconomic status, complete blood count with general blood picture, bone marrow aspiration, Vit B12 level, serum folate, and liver function test were done. A TLC count less than 4000/mm3 and platelet count less than 150000/mm3 was considered as leucopenia and thrombocytopenia respectively. Cases with macrocytic blood picture were included for further evaluation with bone marrow, Vitamin B12 and folic acid level. The diagnosis of megaloblastic anaemia was established by megaloblastic changes in the bone marrow, low serum B12 (100 fl. Out these enrolled patients, bone marrow biopsy was done in 12 cases to confirm the diagnosis. RESULTS Bimodal distribution was observed with more cases among toddlers & early adolescent females. Most of the cases belonged to low socioeconomic status with poor dietary habits. Regarding clinical presentation, anaemia, neurological manifestation, icterus, hepatosplenomegaly, pigmentation were observed. Generalized weakness & anorexia were the commonest symptoms. CONCLUSIONS Besides its high prevalence in infancy and early childhood group, our study shows significant cases of adolescent females who presented as isolated B12 deficiency. These high-risk populations can be supplemented with B12 under national program along with iron and folate.

In the present study, polystyrene:europium (III) oxide polymer films at a ratio of 95:5 wt% were prepared using a solution casting technique. These polymeric films were irradiated with 5, 25 and 50 kGy γ-radiation doses and their thermoluminescence (TL) and thermal properties were studied as a function of radiation dose. Analysis of Fourier transform infrared spectra revealed different modes of vibration and polymer-filler interaction. Reduction of vibrational modes with radiation dose was observed. The TL glow curve intensity was observed to increase with increasing radiation dose and to become broader in the 378 K and 444 K regions. Detrapping of electrons implied by the glow curve was caused by thermally induced macromolecular motion, concurrent with β-relaxation in polystyrene. The TL glow curve parameters were computed using a glow curve deconvolution method. Differential scanning calorimetry analysis indicated that the glass transition temperature (Tg ) increased with increase in dose, suggesting crosslinking of the polymer chain. Scanning electron microscopy analysis evidenced the change in surface morphology due to γ-irradiation.

Polystyrene polymer (PS)/Al2O3 nanocomposite films were synthesized from PS:Al2O3 (1–x):x mixtures (x = 3 wt%) via solution casting method. These nanocomposite films were exposed to 5 MeV proton beam of different fluences. The proton beam induced changes in optical and luminescence properties of PS and PS:Al2O3 films have been investigated using FTIR, UV-visible, Photoluminescence and thermoluminescence studies. FTIR studies concede reduction in the peak intensity due to doping of Al2O3 and proton irradiation. The UV-visible spectra show shifting of absorption edge with increasing fluence. This can be attributed to creation of conjugated system of bonds. The band gap of PS and 3 wt% Al2O3 doped PS is observed to be 4.38 eV and 4.34 eV, respectively, whereas the band gaps of proton irradiated 3 wt% Al2O3 doped PS films are found to be 4.28 eV and 4.23 eV at the fluences of 1 × 1012 ions/cm2 and 1 × 1013 ions/cm2, respectively. The photoluminescence emission spectra show three peaks, wavelength at 411 nm, 435 nm and 462 nm corresponding to the PS in violet-blue region when excited with near UV wavelength of 380 nm. The intensity of emission peaks was found to increase with increasing fluence. The thermoluminescence curves of PS/Al2O3 were analysed using glow curve deconvolution method (GCD). The increase in TL peak intensity of the glow curve was observed as fluence increase.

The production cross-sections of the V 48 , S 47 c , S 46 c , and S 44 m c residues were measured in the proton induced T n a t i reactions using the stack foil activation technique followed by the off-line γ − r a y spectrometry. The present work was carried out at 14UD BARC-TIFR Pelletron accelerator, Mumbai, India. The proton beam of 22 MeV was used for the irradiation of the samples and was degraded along the stack of target foils using aluminum (Al) degraders. The measured cross-section data were compared with the existing literature data available in EXFOR data library. The results were also compared with the theoretical values from the TALYS-1.9 and the ALICE-2014 nuclear model codes using the suitable input level density models. The pre-equilibrium contribution has also been estimated for the populated reaction residues in the present work. The present work offers a comparison between the two theoretical model codes using a similar input level density model. The reaction product S 44 m c also has some practical medical applications in nuclear medicine.

In this article, we present the nuclear excitation functions of the fast neutron-induced reactions 52Cr(n,p)52V, 52Cr(n,α)49Ti, 52Cr(n,2n)51Cr, 56Fe(n,p)56Mn, 56Fe(n,α)53Cr, and 56Fe(n,2n)55Fe, because these measurements are critical to estimate the level of the neutron activation for the fusion reactor structural materials. The theoretical computer codes TALYS-1.8 and EMPIRE-3.2.2 have been used for the calculation of the excitation functions. The theoretical calculations consider different nuclear reaction models, level density models and optical model potentials. The calculated excitation function results are compared with the existing experimental data obtained from the IAEA-EXFOR database, as well as with those available in the TENDL-2017 and ENDF/B-VIII.0-evaluated nuclear data libraries. The obtained results show the variation in excitation functions for different level density models. Moreover, we have studied the contribution from different reaction mechanisms in total reaction cross-section which varies with the incident neutron energy. These excitation function results can be useful to estimate the important parameters of nuclear reactors, such as nuclear heating, nuclear transmutation rates, and waste management etc. This kind of information can enhance the basic understanding of the mechanism of the fast neutron-induced nuclear reactions.

The reaction cross sections of $$^{197}$$ Au(n,2n) $$^{196}$$ Au, $$^{115}$$ In(n,n $$^{\prime })^{115m}$$ In, $$^{232}$$ Th(n,f) $$^{97}$$ Zr, and $$^{238}$$ U(n,f) $$^{97}$$ Zr reactions were measured at different neutron energies using standard neutron activation analysis (NAA) technique followed by off-line $$\gamma $$ -ray spectrometry. The irradiation was performed using the BARC-TIFR Pelletron facility in Mumbai, India. The quasi-monoenergetic neutron beam was generated using the $$^7$$ Li(p,n) $$^7$$ Be reaction. The measured data are compared with available experimental data in the EXFOR database, different evaluated libraries such as ENDF/B-VIII.0, JEFF-3.3, JENDL-4.0, CENDL-3.1, IRDFF II, TENDL-2017 and with the results predicted using nuclear modular code TALYS-1.9. The TALYS-1.9 code was used for a better description of the present work and literature data. The reactions studied in the present paper are considered flux monitor reactions as they are widely used for the measurement of neutron flux in NAA-technique.

The 107Ag(n, 2n)106mAg reaction cross sections at the neutron energies of 10.50 ± 0.68, 13.52 ± 0.67, 16.86 ± 0.58 and 19.86 ± 0.59 MeV were measured by using the off-line γ-ray spectroscopy and activation analysis techniques. The 7Li(p, n) reaction was used to produce the high-energy quasi-monoenergetic neutrons with the proton beam from the 14UD BARC-TIFR Pelletron facilities at Mumbai, India. The neutron flux was monitored using the standard 27Al(n, α)24Na monitor reaction. The detailed uncertainties analysis in the measured cross sections was performed using the covariance analysis. The cross sections were also theoretically calculated using TALYS-1.9 code from 10 to 25 MeV energies. The measured cross-sections data are compared with the evaluated data from TENDL-2019, JENDL-4.0 and ENDF/B-VIII.0 libraries as well as with the existing experimental data available in EXFOR compilation. Our data show good agreement with some of the previous experimental data and with the theoretical values calculated with TALYS-1.9 code. Present work will provide better description of level density models and pre-equilibrium process.

The cross sections of the selenium isotopes 76Se, 77Se, 78Se and 80Se within 10.5–19.81 MeV neutron energy range have been measured through neutron activation method along with off-line γ-ray spectrometry. The quasi-monoenergetic neutrons were produced from the 7Li $$\left( {p, n} \right)$$ reaction at 14UD BARC-TIFR Pelletron Accelerator Facility, Mumbai, India. The statistical codes TALYS-1.9 and EMPIRE-3.2.2 were applied for the theoretical calculation of reaction cross sections with different level density models from 2 to 22 MeV neutron energies. Besides this, the Se $$\left( {n, p} \right)$$ As reaction cross sections were also calculated from different systematic formulae within 14–15 MeV neutron energies. The measured data were compared with existing literature data available in the EXFOR database, evaluated data of ENDF/B-VIII.0, JENDL-4.0 and TENDL-2019 libraries and with theoretical outcomes through TALYS-1.9 and EMPIRE-3.2.2 codes. The uncertainties in existing cross sections were calculated through the method of covariance analysis by including partial uncertainties and correlation among the different attributes. The $$\left( {n, p} \right)$$ reaction cross sections of selenium isotopes at higher neutron energies first time measured in the present work can be added as new data in the nuclear data library.

The cross sections of the 121Sb 120Sbm and 123Sb 122Sb reactions were measured at 12.50, 15.79 and 18.87 MeV neutron energies relative to the standard 27Al 24Na monitor reaction using neutron activation and offline γ-ray spectrometry. Irradiation of the samples was performed at the BARC-TIFR Pelletron Linac Facility, Mumbai, India. The quasi-monoenergetic neutrons were generated via the 7Li reaction. Statistical model calculations were performed by nuclear reaction codes TALYS (ver. 1.9) and EMPIRE (ver. 3.2.2) using various input parameters and nuclear level density models. The cross sections of the ground and the isomeric state as well as the isomeric cross section ratio were studied theoretically from reaction threshold to 26 MeV energies. The effect of pre-equilibrium emission is also discussed in detail using different theoretical models. The present measured cross sections were discussed and compared with the reported experimental data and evaluation data of the JEFF-3.3, ENDF/B-VIII.0, JENDL/AD-2017 and TENDL-2019 libraries. A detailed analysis of the uncertainties in the measured cross section data was performed using the covariance analysis method. Furthermore, a systematic study of the reaction cross section for 121Sb and 123Sb isotopes was also performed within 14–15 MeV neutron energies using various systematic formulae. This work helps to overcome discrepancies in Sb data and illustrate a better understanding of pre-equilibrium emission in the reaction channel.

The neutron capture cross sections of 232Th and 238U at the average neutron energies of 5.08 ± 0.17, 8.96 ± 0.77, 12.47 ± 0.83, and 16.63 ± 0.95 MeV have been measured by using the activation technique and off-line γ-ray spectroscopy. The 232Th and 238U were irradiated with neutrons produced from the 7Li(p, n) reaction using the proton energies of 7, 11, 15 and 18.8 MeV from the 14UD BARC-TIFR Pelletron facility in Mumbai, India. Detailed covariance analysis was also performed to evaluate the uncertainties in the measured cross-sections. The excitation function of the 232Th(n, γ) and 238U(n, γ) reactions were calculated using the theoretical model code TALYS-1.9. The experimental and theoretical results from the present work were compared with the ENDF/B-VII-1 and JENDL-4.0 nuclear data libraries and were found to be in good agreement.

In the present study, europium (III) oxide (Eu2 O3 )-doped polystyrene (PS) polymer films were synthesized using a solution-casting technique for different filler levels. These films were irradiated with 5, 25 and 50 kGy γ doses and characterized using various techniques, viz. X-ray diffraction (XRD), and UV-visible and photoluminescence (PL) spectroscopies as a function of composition level and radiation dose. The UV-visible spectra indicated a decrease in the optical direct band gap of composite films with increasing concentrations of dopant and radiation dose. The band gaps of composites obtained using Tauc's equation were found to be 4.38, 4.37, 4.36 and 4.34 eV for 0, 1, 3 and 5% Eu2 O3 -doped PS respectively, while the band gaps of 5% Eu2 O3 -doped PS polymer films irradiated with 5, 25 and 50 kGy were found to be 4.30, 4.26 and 4.21 eV, respectively. Photoluminescence (PL) emission spectra showed the characteristic peaks of Eu3+ at 595 nm, 612 nm and 617 nm with an excitation wavelength of 247 nm. The intensity of characteristic peaks of Eu3+ was observed to increase with increasing filler concentration, while it was found to decrease with increasing radiation dose. The polymer under study may be useful in accidental dosimetry. As photoluminescence studies are carried out after a gap of 200 h from irradiation and PL emission of γ-irradiated polymer yielded 10 times emission when compared with non-irradiated polymer.

In the present work, a simple solution casting method was utilized to synthesize aluminium oxide (Al2O3) doped polystyrene (PS) polymer nanocomposite films. As synthesized films were characterized using X-ray diffraction (XRD), Fourier transform infrared (FTIR) spectroscopy, ultra violet (UV)-visible spectroscopy, photoluminescence (PL) method and scanning electron microscopy (SEM). The crystalline nature of the films was found to decrease after incorporation of filler in the polymer matrix as revealed by XRD results. A new carbonyl group was appeared in the FTIR spectra and confirmed the charge transfer reaction between filler and polymer matrix. The decrease in the band gap was found with the filler concentration in the synthesized polymer nanocomposite films. Photoluminescence emission spectra of nanocomposites were observed at 411 nm, 435 nm and 462 nm, respectively in violet-blue region which indicates interaction between the dopant and the polymer matrix. The PL emission spectra of polymer nanocomposite films with 3 wt% of Al2O3 filler exhibited higher peak intensity. The Al2O3 filler dispersion is found to reduce band gap and promote luminescence property in polystyrene. SEM analysis indicates the agglomeration of Al2O3 nanoparticles into PS matrix at higher concentration.

The compound Nb3Sn possess superconductivity at suitable temperatures, therefore, it is best suited to be used in the toroidal coils of superconducting magnets which holds the fusion plasma and confine it inside the reactor core. The neutron induced reaction cross-sections are required from threshold to 20 MeV for different isotopes of Tin (Sn). Since limited data is available for the reactions with the Sn isotopes. Therefore, we have optimized the (n, p) and (n, 2 n) reaction cross-sections for all possible Sn isotopes from threshold to 20 MeV with modified input parameters in the nuclear reaction modular codes EMPIRE-3.2.2 and TALYS-1.8. These codes account for the major nuclear reaction mechanisms, including direct, pre-equilibrium, and compound nucleus contributions. The present results from 116 Sn ( n , p ) 116 m In , 117 Sn ( n , p ) 117 In , 117 Sn ( n , p ) 117 m In , 118 Sn ( n , 2 n ) 117 m Sn , 120 Sn ( n , 2 n ) 119 m Sn and 124 Sn ( n , 2 n ) 123 m Sn reactions calculated with nuclear modular codes: TALYS – 1.8, EMPIRE – 3.2.2 were compared with EXFOR data, systematics proposed by several authors and with the existing evaluated nuclear data library ENDF/B-VII.1, as well. The results from the present study can be used for the future development of ITER devices as well as to upgrade the nuclear model codes.

Objectives: To carry out a survey among dentists to assess the awareness about radiation protection, attitude of the practitioner toward radiation protection, methods of radiation protection being used, and type of radiographic equipment being used in dental practice. Materials and Methods: A research was conducted among 1000 dentists who were using dental radiology. A review of literature of several articles related to the research was done. After analysis of these articles was done, a 33 question-long questionnaire was prepared. The questionnaire was then distributed among the dentists. The dentists were informed about the anonymous processing of the questionnaires. Once the questionnaires were completed, they were collected in person, the answers were tabulated, and were then sent for statistical analysis. Results: A total of 1394 dentists were approached for this study; however, only 1000 dentists returned our questionnaire. The overall correct knowledge of dentists regarding safety standards of dental radiology was found to be 29.9%. The overall correct attitude of dentists regarding safety standards of dental radiology was found to be 76.3%. The overall correct practice of dentists regarding safety standards of dental radiology was found to be 19.8%. Conclusion: On the basis of the result of the study conducted, we concluded that the dentists should be made aware about the adverse effects of radiation exposure, and as the overall compliance of the dentist is low, Continuing Dental Education programs should be conducted in order to educate dentists who are already using X-ray machines and to keep them updated with the latest technology.

Effect of swift heavy ion irradiation on electrical and optical properties of chitosan-based solid polymer electrolyte system, prepared by the solution casting technique, was investigated. The solid polymer electrolyte films were irradiated with C +5 and Ni +7 ions of energy 60 and 100 MeV, respectively, at different fluences. X-ray diffraction (XRD) analysis revealed the transformation of chitosan structure to the amorphous phase due to the addition of salt. FTIR spectra showed diverse vibrational modes and scissioning of bonds due to ion beam irradiations. Ions produce volatile low-molecular-weight species and results in the evolution of gas during irradiation processes. The polymer electrolyte became carbon rich with more conjugated bonds and diminished the band gap, as found by the UV–Vis analysis. The variable parameters obtained by the Bergman fitting specify that the relaxation process in the polymeric matrix is non-Debye, and the conductivity of electrolyte enhanced as a function of beam parameters.

BACKGROUND The purpose of this observational study was to study aetiological factors associated with low birth weight newborns. MATERIALS AND METHODS This study was conducted as a cross-sectional study using data from women who had delivered their children at Dr. Susheela Tiwari Government Hospital. This study was conducted on 202 female patients. The newborns were divided into 2 categories based on birth weight as those with a birth weight of 2.5 kg and above and those with a birth weight of less than 2.5 kg based on gestational age. The data were collected by interviews with the mothers, abstraction of medical records and anthropometry. RESULTS The incidence of Low Birth Weight (LBW) was higher in anaemic mothers with p value 0.026. 43% of women were primigravida in LBW while in Normal Birth Weight (NBW) there was 26%. In the study, 18% mothers were passive smoker in NBW babies and 34% mothers were passive smoker in LBW babies. Birth interval in NBW babies was 24.2 weeks (mean) and it was 20.1 weeks in LBW babies with p value 0.028. CONCLUSION Anaemia, short birth interval, passive smoking, low maternal age and primiparity are significant risk factors for LBW.

Aluminum oxide nanoparticles were incorporated into polystyrene using solution casting method. The films so obtained were irradiated with gamma rays using 60Co source. The radiation induced luminescence properties of the polymeric films were studied using UV-visible and photoluminescence spectroscopies. UV-Visible studies reveal enhancement of band gap upon gamma irradiation which could be ascribed to increased defects in the polymer matrix. The photoluminescence spectra of PS/Al2O3 show broad peaks around 410, 435 and 461 nm with the excitation wavelength of 380 nm. The peak height is found to diminish with increasing radiation dose. PL spectra show significant shifting of the highest intensity position due to gamma radiation.

Polystyrene polymer (PS)/Al

The production cross sections for the medical isotope $^{99}\mathrm{Mo}$ were measured using the $^{100}\mathrm{Mo}(n,2n)$ reaction at average neutron energies of $10.95\ifmmode\pm\else\textpm\fi{}0.45, 13.97\ifmmode\pm\else\textpm\fi{}0.68, 16.99\ifmmode\pm\else\textpm\fi{}0.53$, and $20.00\ifmmode\pm\else\textpm\fi{}0.58$ MeV using offline $\ensuremath{\gamma}$-ray spectroscopy. The neutron beam was generated using the $^{\mathrm{nat}}\mathrm{Li}(p,n)$ reaction at the 14UD BARC-TIFR Pelletron facility, Mumbai, India. The uncertainties in the measured data were calculated using covariance analysis. The experimental results were compared with the existing data libraries ENDF/B-VII.1, JENDL-4.0, JEFF-3.2, and CENDL-3.1. The present results were also reproduced and compared with the theoretical nuclear model codes talys-1.9 and alice-2017 using different input descriptions. A modified set of parameters were also used in talys-1.9 to fit the existing data more accurately. The present findings show a good agreement with the theoretical predictions and with the existing experimental results from the different data libraries. In addition to this, a comparative study have also been performed between the literature data of $(n,p), (n,2n)$, and $(n,\ensuremath{\alpha})$ reaction cross sections at 14.5 MeV using various systematic formulas. The outcomes of the present work are important for the advancement of medical accelerators, dosimetry, and fast reactor systems.

The 58Ni(n, p) and 58Ni(n, 2n) reaction cross-sections were measured from threshold to 18MeV neutron energies using the activation and off-line $\gamma$ -ray spectroscopic technique. The quasi-monoenergetic neutron beam was generated using the 7Li(p, n) reaction. The results from the present work were compared with those of the literature and with the evaluated data from different libraries, like ENDF-B/VII.1, JENDL-4.0, CENDL-3.1, and JEFF-3.3. Nuclear model codes, like TALYS-1.9 and EMPIRE-3.2.3-Malta, were also used for a better description of the present work and literature data. The uncertainties in the measured cross-section were evaluated using the covariance analysis. The present experimental results were found to be in good agreement with those of the literature and with the evaluated data. The nuclear model code TALYS-1.9 was found successful in reproducing the experimental data for both reactions. However, the EMPIRE-3.2.3-Malta model code was found to be able to reproduce only the trend of the 58Ni(n, p) reaction excitation function. The present work provides a better insight on the comparison of both nuclear model codes. The present work is also essential for the production cross-section and the dose rate estimation of the medical isotope 58Co.

The cross-sections for

State of the art applications (nuclear waste host, scintillators, piezoelectric, SOFCs, etc.) of isometric pyrochlore, A2B2O7, are very sensitive to the structural assessment upon ion irradiation. In the present study, La2Zr2O7 is irradiated using 1 MeV Xe4+ ions with fluence of 1 × 1013, 5 × 1013, and 1 × 1014 ions/cm2 at ~ 88 K and 300 K. The impact of irradiation temperature and ion fluence on the structural properties of the La2Zr2O7 are investigated using the GIXRD, Raman spectroscopy and high resolution transmission electron microscopy (HR-TEM). The GIXRD and Raman results indicate that the degradation of the crystallinity (i.e., damage/amorphization) are significantly higher with enhanced fluence at ~ 88 K than that of 300 K. The induced lattice strain also increases with an increase of ion fluence and it is more pronounced at ~88 K. The HR-TEM results of the La2Zr2O7 samples exhibit that degradation of the atomic ordering are more pronounced at ~ 88 K. The prominent induced strain and degradation of crystallinity (i.e., damage/amorphization) at ~ 88 K appear to be ion fluence and irradiation temperature-dependent. This study is enlightening the effect of the ion fluence and irradiation temperature on the degradation of crystallinity (i.e., damage/amorphization).

Self-sustained films of biodegradable chitosan (CS) and chitosan-Ag nanocomposites (CSN) were prepared by chemical route followed by C+5 and Ni+7 ions irradiation with varying fluences. The crystallite size decreased from 11.1 to 2.7 nm for CS and 17.6 to 14.2 nm for CSN with increasing ions fluence as observed from the analysis of X-ray Diffraction (XRD) spectra. ATR-FTIR spectra revealed assorted vibrational modes and degradation of polymeric chains in both, CS and CSN matrices upon irradiation. The molecular interactions between main and side-chain functional groups impeded due to nanoparticles confining effects. MeV ions yield low-molecular-weight fragments with degassing of some volatile gaseous species during irradiation. An acute amendment in absorption spectra ascribed to change in surface color and differential absorbance at the wavelength of 370 nm showing blocking of UV radiation. The formation of conjugated linkages and carbonization of CS and CSN matrices lead to decrease in bandgap. Modifications in the physicochemical properties were found to be in persuasive association with changes in frequency-dependent dielectric responses. The shape parameter was moderately decreased and indicating non-Debye relaxation. The conductivity of CS and CSN matrices enhanced and follows the universal dielectric response. The amendment in surface morphology was also revealed upon irradiation.

Poly ethylene oxide (PEO) films were synthesized by solution cast method. These self-standing films were exposed with 60 MeV C +5 ion and 100 MeV Ni +7 ion at different fluences. SHI induced effect was investigated by employing various techniques. The crystalline size decreased upon irradiation as observed from XRD analysis. FTIR analysis reveals the decrement in the peak intensity upon irradiation. Tauc’s method was used to determine the optical band gap ( E g ), which shows decreasing trends with increase of fluence. The dielectric properties were investigated in the frequency range 10 Hz to 10 MHz for unirradiated and irradiated films. The dielectric constant remains same for the broad-spectrum of frequency and increases at lower frequency. The dielectric loss also moderately influence as a function of frequency due to irradiation. DSC analysis validated the results of XRD. Scanning electron microscopy (SEM) reveals that there is significant change in the surface morphology due to irradiation.

The multinucleon transfer reaction or incomplete fusion reaction (ICF) is a powerful tool to study fission of exotic nuclei that cannot be formed by stable heavy-ion fusion reactions. In the present work, mass distributions of fission fragments (FFs) from fissioning nuclei $^{241,242,243,244}\mathrm{Pu}$ and $^{240,241}\mathrm{Np}$ populated in multinucleon transfer or ICF reactions on $^{6,7}\mathrm{Li}+^{238}\mathrm{U}$ systems have been studied. Among these, $^{244}\mathrm{Pu},\phantom{\rule{0.16em}{0ex}}^{243}\mathrm{Pu}$, and $^{241}\mathrm{Np}$ are formed by the capture of unstable nuclei $^{6}\mathrm{He},\phantom{\rule{0.16em}{0ex}}^{5}\mathrm{He}$, and $t$, respectively, by the target $^{238}\mathrm{U}$. Identification of fissioning nuclei and determination of excitation energies have been performed by finding the details of the outgoing projectile-like fragments detected in coincidence with both the fission fragments on an event-by-event basis. The measurements of FF mass distributions and FF folding angle distributions of different ICF channels confirm that these channels are the prime factors for the modifications in the experimental ratio of asymmetric to symmetric fission yields and the width of folding angle distributions for inclusive fission reported earlier on the same reactions. Comparison among the ratio of asymmetric to symmetric fission yields from $^{241,242,243,244}\mathrm{Pu}$ and $^{240,241}\mathrm{Np}$ nuclei formed in the present reactions, available literature data, and the theoretical calculations using gef code shows that the shell correction for symmetric fission channels plays an important role in describing the experimental mass distribution.

The cross sections for the $^{232}\mathrm{Th}(n,\ensuremath{\gamma})$ reaction have been measured in the neutron energy range of 11--19 MeV by using activation and offline $\ensuremath{\gamma}$-ray spectrometric techniques. The neutrons of desired energy were obtained by the $^{7}\mathrm{Li}(p,n)$ reaction using a proton beam of 13--21 MeV from the 14UD BARC-TIFR Pelletron facility at Mumbai, India. The $^{232}\mathrm{Th}(n,\ensuremath{\gamma})$ 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).

The neutron capture cross sections of

The production cross-sections for the medical isotope 99Mo were measured using 100Mo(n, 2n) reaction at average neutron energies of 10.95 ± 0.45, 13.97 ± 0.68, 16.99 ± 0.53 and 20.00 ± 0.58 MeV using the off-line γ-ray spectroscopy. The neutrons of desired energies were generated using 7Li (p, n) reaction at 14UD BARC-TIFR Pelletron facility, Mumbai, India. The experimentally measured data from the present work have been compared with the existing data libraries like, ENDF/B-VII.1, JENDL-4.0, JEFF-3.2 and CENDL-3.1. The results were also reproduced and compared with the theoretical nuclear modular codes like TALYS-1.8, and ALICE-2014. A modified set of parameters is also used to fit the existing data more accurately. The present findings show a good agreement with the theoretical as well as with the existing experimental data in different data libraries.

In the present study, europium (III) oxide (Eu

We measured neutron emission spectra for $^{19}\mathrm{F}$-induced reactions on $^{181}\mathrm{Ta}$, $^{89}\mathrm{Y}$, and $^{51}\mathrm{V}$ at beam energies of 130, 140, 145, and 150 MeV. Measurements were made using liquid scintillator detectors at eight angles in the range of ${25}^{\ensuremath{\circ}}\ensuremath{-}{143}^{\ensuremath{\circ}}$ using time-of-flight and pulse-shape discrimination. A comparison has been made with alice2014 and pace4 calculations to understand the role of incomplete fusion and pre-equilibrium effects. Global predictions with alice2014 without parameter adjustment gives a fair agreement with the measured data.

In order to study structural, thermal, optical and dielectric behaviors of composites, the films of Cu/polystyrene nanocomposites were synthesized at different concentrations of Cu-nanoparticles. These polymer nanocomposites were irradiated with carbon (85 MeV) and silicon (120 MeV) ions at different fluences. The samples were characterized using different techniques viz: X-ray diffraction, UV-visible spectroscopy, differential scanning calorimetry, and impedance gain phase analyzer. A noticeable increase in the intensity of X-ray diffraction peaks was observed after irradiation with 120 MeV Si-ions, which may be attributed to radiation-induced cross-linking in polymer. Optical properties like band gap was estimated for pure polymer and nanocomposite films from their optical absorption spectra in the wavelength region 200-800 nm. It was found that the band gap value shifted to lower energy (from 4.38 eV to 3.40 eV) on doping with silver nanoparticles and also upon irradiation. Differential scanning calorimetry analysis revealed an increase in the glass transition temperature upon irradiation, which may be attributed to cross linking of polymer chain due to ion beam irradiation which is also corroborated with XRD analysis. Dependence of dielectric properties on frequency, ions and filler concentration was studied. The results revealed the enhancement in dielectric properties after doping nanoparticles and also upon irradiation. It was observed that the effect of Si-beam is more effectual than the C-beam because of large electronic energy loss of heavy ion.

The 197Au(n, γ)198Au reaction cross-sections at the neutron energies of 1.12, 2.12, 3.12 and 4.12 MeV were determined by using activation and off-line γ-ray spectrometric technique. The mono-energetic neutron energies of 1.12–4.12 MeV were generated from the 7Li(p, n) reaction by using the proton energies of 3 and 4 MeV from the folded tandem ion beam accelerator (FOTIA) at BARC as well as 5 and 6 MeV from the Pelletron facility at TIFR, Mumbai. The 115In(n,γ)116mIn reaction cross-section was used as the neutron flux monitor. The 197Au(n, γ)198Au reaction cross-section at the neutron energies of 3.12 and 4.12 MeV are reported for the first time. The 197Au(n, γ)198Au reaction cross-sections at 1.12 and 2.12 MeV are close to the literature data of in between neutron energies. The 197Au(n, γ)198Au cross-section was also calculated theoretically by using the computer code TALYS 1.6 and found to be higher than the experimental data of present work and literature data within the neutron energies of 0.8 to 4 MeV.

Wilson’s Disease (hepatolenticular degeneration) is a rare, autosomal recessive disorder that can be associated with degenerative changes in the brain, liver disease, and Kayser-Fleischer rings in the cornea. The incidence is 1 in 50000 birth worldwide. It is caused by a mutation in the copper-transporting gene, ATP7B. The diagnosis depends primarily on the clinical features, the biochemical parameters and the presence of the Kayser – Fleischer ring. It is progressive and potentially fatal if untreated; specific effective treatment is available. Here, we are reporting two cases which were affected by Wilson’s disease, with only neurological manifestations, without any hepatic involvement or derangement. We also present here a review of literature on Wilson’s disease.

Background Autoimmune diseases such as rheumatoid arthritis (RA) are the consequence of a persistent imbalance between pro- and anti-inflammatory immune mechanisms, leading to chronic inflammation. The objective of this study was to determine whether the high sensitive C-reactive protein (hs-CRP) and cytokines are elevated in RA patients and to investigate the relationship between these markers and disease activity in RA, measured by disease activity score 28 (DAS28). Methods We studied 110 RA patients according to American College of Rheumatology revised criteria for RA, and 55 controls matched by age and sex. Serum levels of hs-CRP and cytokines interleukin (IL)-6, IL-10 and tumour necrosis factor-a (TNF-a) were estimated and correlated with the DAS28. Serum hs-CRP was assayed immunoturbidimetrically and cytokines were analysed by commercially available ELISA kit. Results We found that RA patients had significantly higher levels of serum hs-CRP (p < 0.001), IL-6 (p < 0.001), TNF-a (p < 0.001), and IL-10 (p < 0.01) as compared to healthy controls. hs-CRP, IL-6 and TNF-a correlated positively (p < 0.001) and IL-10 correlated negatively (p < 0.01) with DAS28. Conclusions These results demonstrate that RA patients have high levels of inflammatory markers, and these levels are correlated with the DAS28. These findings suggest a possible role of these markers in the pathogenesis of RA. Moreover, these biomarkers can be used as markers of disease activity in the diagnosis and treatment of RA.

Transfer-induced fission fragment angular distribution measurements have been carried out in $^{6}\mathrm{Li}+^{238}\mathrm{U}$ reaction at beam energies of 36 and 40 MeV in coincidence with projectile-like fragments. The fission fragment anisotropies for $\ensuremath{\alpha}$- and deuteron-transfer-induced fission reactions are obtained with respect to the recoil direction. The anisotropy values for transfer-induced fissions are observed to be either similar or lower than the inclusive measurement. In order to quantitatively understand the present experimental data on transfer-induced fission, anisotropy values have been compared with the preequilibrium fission model considering ground-state spin of the projectile and/or target. It is found that the model predicts the inclusive and exclusive anisotropy data reasonably well.

The cross sections of the $^{186}\mathrm{W}(n,\ensuremath{\gamma})^{187}\mathrm{W}, ^{183}\mathrm{W}(n,p)^{183}\mathrm{Ta}$ and $^{154}\mathrm{Gd}(n,2n)^{153}\mathrm{Gd}, ^{160}\mathrm{Gd}(n,2n)^{159}\mathrm{Gd}$ reactions were measured at the neutron energies $5.08\ifmmode\pm\else\textpm\fi{}0.165, 8.96\ifmmode\pm\else\textpm\fi{}0.77, 12.47\ifmmode\pm\else\textpm\fi{}0.825$, and $16.63\ifmmode\pm\else\textpm\fi{}0.95\phantom{\rule{0.16em}{0ex}}\mathrm{MeV}$. Standard neutron activation analysis technique and off-line $\ensuremath{\gamma}$ ray spectrometry were used for the measurement and analysis of the data. Measurements were done in the energy range where few or no measured data are available. The results from the present work are compared with the literature data based on the EXFOR compilation. The experimental results are supported by theoretical predictions using nuclear modular codes TALYS 1.8 and EMPIRE 3.2.2. The predictability of different one-dimensional models available in TALYS 1.8 and Levden models in EMPIRE 3.2.2 were tested. A detailed comparison of experimental results with theoretical model calculations is made.