Search

The cross sections of the 60Ni(p,n)60Cu reaction from threshold energy to ~ 20 MeV have been measured by employing stack foil activation technique and off-line γ-ray spectrometry. The uncertainties for the reaction cross sections have been estimated by applying covariance analysis and least square method. The measured cross-sections are found to be in agreement with most of the literature data available in EXFOR database. The excitation function of the 60Ni(p,n)60Cu reaction was also theoretically calculated by using the TALYS-1.9 code. The excitation functions of 60Ni(p,n)60Cu reaction from TALYS-1.9 and TENDL-2017 follow a similar trend as of the experimental data of present work and literature but are little higher around the peak cross-section region.

The average cross-sections for the 160Gd(γ,n)159Gd and 142Ce(γ,n)141Ce reactions have been measured relative to the cross-section of 197Au(γ,n)196Au reaction at the bremsstrahlung end-point energy of 10 MeV. The average cross-sections of 160Gd(γ,n)159Gd and 142Ce(γ,n)141Ce reactions were determined using an off-line γ-ray spectrometric technique and were found in close agreement with the literature data. The uncertainties of the measurements have been studied using covariance analysis of the experimental data for the photo-nuclear reactions. Both 159Gd and141Ce are the beta emitting radio-nuclides with short half-life, which makes them perfect elements for nuclear medicinal purposes, like radio-imaging and for metastatic bone tumour.

The radionuclide 99Mo has been prepared by 100Mo(γ, n) reaction using two types of natural molybdenum compound (molybdenum trioxide and zirconium molybdate gel) with the bremsstrahlung end-point energies of 10 and 15 MeV. After the equilibrium, 99mTc was separated as NaTcO4 from the irradiated samples using two different chemical procedures to examine the chemical yield. The separated Na[99mTc]TcO4 from the ZrMo gel has the 99Mo breakthrough of 99 % as well as chemical impurities of Al, Mo and Zr

The 151Eu(n,γ)152m1Eu reaction cross-section at the neutron energies (E n ) of 1.12, 2.12, 3.12 and 4.12 MeV was determined by using activation and off-line γ-ray spectrometric technique. The mono-energetic neutrons of 1.12–4.12 MeV were generated from the 7Li(p,n) reaction by using the proton beam energies of 3–6 MeV. The 197Au(n,γ)198Au reaction cross-section was used as the neutron flux monitor. The 151Eu(n,γ)152m1Eu reaction cross-section was also calculated by using computer code TALYS 1.6 and compared with the experimental data to check its validity. The Eu(n,γ) reaction cross-section is important for the safety of the fast reactor and conventional fission reactor.

The 110Cd(n,γ)111mCd and 111Cd(n,n′)111mCd reaction cross-sections at the neutron energies of 1.12, 2.12, 3.12 and 4.12 MeV were determined for the first time by using activation and off-line γ-ray spectrometric technique. The values from preset work and literature data at other neutron energies are compared with the theoretical values based on TALYS 1.6 and found to be in agreement. The formation cross-section of 111mCd from the (n,γ) and (n,n′) reaction of natCd is important for neutron economy and estimation of dose of the Cd control rod use in the reactor.

The separation characteristics of hydrogen-tritium mixtures by gas chromatography at 77 K have been studied using molecular sieve 4A, coated with 5 wt% vanadium in the form of V2O4, as supporting material. The performance of the column was found to be better than that observed on the conventional coated and uncoated molecular sieves in terms of reduced retention times, resolution, nature of the peak and added thermal stability of the stationary phase.