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Excitation functions for the formation of the radionuclides 51Cr, 52Mn and 54Mn via deuteron-induced activation of natural iron were measured up to deuteron energies of 35 MeV. The available experimental databases of the reaction products 51Cr, 52Mn and 54Mn were extended and compared with the nuclear model calculations using the TALYS code. The model calculations reproduce our measured data after a careful choice of the input model parameters. Some information obtained on competition between the emission of multinucleons and a bound α-particle. [ABSTRACT FROM AUTHOR]

Excitation functions of the reactions 27Al(d,αp)24Na, 27Al(d,2p)27Mg and 27Al(d,p)28Al were measured by the activation technique up to deuteron energies of 37 MeV. The available experimental databases of the reaction products 27Mg and 28Al were extended and compared with the nuclear model calculations based on the code TALYS-1.8. Our measured data are reproduced well by the model calculations after adjustment of a few free input parameters. The cross-section ratio of the (d,αp) to (d,2p) process as a function of projectile energy was deduced from the measured data, and the result is interpreted in terms of competition between a proton and an α-particle emission.

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. [ABSTRACT FROM AUTHOR]

For Th and U, the (n ,γ) reaction cross-sections at the neutron energies of 2.45 and 14.8 MeV as well as the (n,2n) reaction cross-sections at 14.8 MeV have been determined using activation and off-line γ-ray spectrometric technique. The (n ,γ) and (n,2n) reaction cross-sections of Th and U were also calculated theoretically using the TALYS 1.6 computer code. The present data and literature data in a wide range of neutron energies were compared with the evaluated data of ENDF/B-VII.1, JENDL-4.0, JEFF-3.1/A and CENDL-3.1 and theoretical value of TALYS to examine the systematics of (n ,γ) and (n,2n) reaction cross-sections. [ABSTRACT FROM AUTHOR]

The independent isomeric yield ratios of Pm from the Sm(γ, x) reaction at the end-point bremsstrahlung energy of 45-64 MeV have been determined using an off-line γ-ray spectrometric technique at the 100 MeV electron linac of Pohang accelerator laboratory, Pohang, Korea. We also have determined the isomeric yield ratios of Pm from the Nd(p,xn) reactions in the proton energy of 5.08-44.72 MeV by a stacked-foil activation and an off-line γ-ray spectrometric techniques at the MC-50 cyclotron of the Korean Institute of Radiological and Medical Sciences, Korea. The determined isomeric yield ratios of Pm were compared with literature data and theoretical values estimated by the TALYS 1.4. The present data along with the similar data from literature at other energies shows that the isomeric yield ratio of Pm increases with the excitation energy both in the Sm(γ, x) and the Nd(p, xn) reactions. The isomeric yield ratios of Pm from the Nd(p, xn) reactions are always higher than those from the Sm(γ, x) reactions at the same excitation energy, which indicate the role of input angular momentum besides excitation energy. [ABSTRACT FROM AUTHOR]

The 96Zr( γ, n)95Zr reaction cross-section was experimentally determined at end point bremsstrahlung energies of 10 and 12.5 MeV using off-line γ-ray spectrometric technique. The cross-section increases sharply from the end point energy of 10 to 12.5 MeV, which indicates the role of excitation energy. The reaction cross-section as a function of photon energy was also calculated theoretically using the TALYS 1.2 computer code. The flux weighted average value of the 96Zr( γ, n)95Zr reaction cross-section for the end-point bremsstrahlung energies of 10 and 12.5 MeV was also calculated using the experimental and theoretical data of mono-energetic photons to compare with the present data. The cross-section given in the present work at end- point bremsstrahlung energy of 10 MeV is closer to the flux-weighted value of TALYS but higher than the literature data. On the other hand, at 12.5 MeV, it is higher than the flux weighted value of TALYS and the literature data. [ABSTRACT FROM AUTHOR]

Abstract: The photo-neutron cross-sections of 93Nb at the end-point bremsstrahlung energies of 12, 14 and 16 MeV as well as 45, 50, 55, 60 and 70 MeV have been determined by the activation and the off-line γ-ray spectrometric techniques using the 20 MeV electron linac (ELBE) at Helmholtz-Zentrum Dresden-Rossendorf (HZDR), Dresden, Germany, and 100 MeV electron linac at Pohang Accelerator Laboratory (PAL), Pohang, Korea. The 93Nb(γ, xn, ) reaction cross-sections as a function of photon energy were also calculated using computer code TALYS 1.4. The flux-weighted average values were obtained from the experimental and the theoretical (TALYS) values based on mono-energetic photons. The experimental values of present work are in good agreement with the flux-weighted theoretical values of TALYS 1.4 but are slightly higher than the flux-weighted experimental data of mono-energetic photons. It was also found that the theoretical and the experimental values of present work and literature data for the 93Nb(γ, xn) reaction cross-sections increase from the threshold values to a certain energy, where other reaction channels opens. However, the increase of 93Nb(γ, n) and 93Nb(γ, 2n) reaction cross-sections are sharper compared to 93Nb(γ, 3n) and 93Nb(γ, 4n) reaction cross-sections. The sharp increase of 93Nb(γ, n) and 93Nb(γ, 2n) reaction cross-sections from the threshold value up to 17–22 MeV is due to the Giant Dipole Resonance (GDR) effect besides the role of excitation energy. After a certain values, the individual 93Nb(γ, xn) reaction cross-sections decrease with increase of bremsstrahlung energy due to opening of other reaction channels. [Copyright &y& Elsevier]

Cross sections for (γ, n) reaction at bremsstrahlung end point energies of 10 and 12.5MeV on niobium have been measured by the activation technique. Induced activities were measured by a high-resolution γ-ray spectrometer with a high-purity germanium (HPGe) detector. Theoretically the (γ, n) cross-section of 93Nb as a function of photon energies were also calculated using TALYS 1.4 computer code. We compared the measured data with the flux weighted average values from the available literature data based on experiments with mono-energetic photons and the theoretical calculation by the model code TALYS 1.4. The experimental values are found to be in good agreement with the theoretical value from TALYS 1.4 but are slightly higher than the flux-weighted values from mono-energetic photons [ABSTRACT FROM AUTHOR]

The U(n, γ)U reaction cross-section at average neutron energy of 3.7 ± 0.3 MeV from the Li(p, n)Be reaction has been determined using activation and off-line γ-ray spectrometric technique. The U(n, γ)U and U(n, 2n)U reaction cross-sections at average neutron energy of 9.85 ± 0.38 MeV from the same Li(p, n)Be reaction have been also determined using the above technique. The experimentally determined U(n, γ)U and U(n, 2n)U reaction cross-sections were compared with the evaluated data of ENDF/B-VII, JENDL-4.0, JEFF-3.1 and CENDL-3.1. The experimental values were found to be in general agreement with the evaluated value based on ENDF/B-VII, and JENDL-4.0 but not with the JEFF-3.1 and CENDL-3.1. The present data along with literature data in a wide range of neutron energies were interpreted in terms of competition between different reaction channels including fission. The U(n, γ)U and U(n, 2n)U reaction cross-sections were also calculated theoretically using the TALYS 1.2 computer code and were also found to be in agreement experimental data. [ABSTRACT FROM AUTHOR]

The reaction cross-sections for Ni( n, γ) Ni at E = 0.025 eV and Ni ( n, p) Co at E = 3.7 MeV have been experimentally determined using activation and off-line γ-ray spectrometric technique. The thermal neutron flux used is from the thermal Column of the reactor APSARA at BARC, Mumbai, whereas the neutron energy of 3.7 MeV is from the Li( p, n) reaction at Pelletron facility, TIFR, Mumbai. The Ni( n, γ) Ni and Ni( n, p) Co reactions cross-sections from present work are compared with the available literature data and found to be in good agreement. The Ni( n, p) Co reaction as a function of neutron energy is also calculated theoretically using TALYS computer code version 1.2 and found to be higher than the experimental data. [ABSTRACT FROM AUTHOR]

The Mo(γ, n) reaction cross-section was experimentally determined at end point bremsstrahlung energy of 10 and 12.5 MeV using off-line γ-ray spectrometric technique. It was also found that Mo(γ, n) reaction cross-section increases sharply from the end point bremsstrahlung energy of 10 MeV to 12.5 MeV, which may be because of GDR around the energy region of 12-16 MeV. The Mo(γ, n) reaction cross-section as a function of photon energy was calculated theoretically using TALYS 1.2 computer code. The flux-weighted average values of Mo(γ, n) reaction cross-section for bremsstrahlung having end point energy of 10 and 12.5 MeV were also calculated using the experimental and theoretical data of mono-energetic photon. The present experimental Mo(γ, n) reaction cross-sections were compared with the bremsstrahlung flux-weighted average values of experimental and theoretical data and found to be in the lower side for 10 MeV and in the higher side for 12.5 MeV. [ABSTRACT FROM AUTHOR]