Measurement of bremsstrahlung-induced reaction cross-section for 93Nb using electron Linac
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R. Crasta
, H. Naik, S. V. Suryanarayana
, S. Ganesh , P. M. Prajapati , M. Kumar , T. N. Nathaniel , V. T. Nimje , K. C. Mittal und A. Goswami
Summary
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
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Artikel in diesem Heft
- Measurement of bremsstrahlung-induced reaction cross-section for 93Nb using electron Linac
- Electrolytic partitioning of uranium and plutonium based on a new type of electrolytic mixer-settler
- Influence of humic acid on neptunium(V) sorption and diffusion in Opalinus Clay
- Quantum chemical study of inner-sphere complexes of trivalent lanthanide and actinide ions on the corundum (110) surface
- Synthesis and preliminary pharmacological evaluation of a new putative radioiodinated AMPA receptor ligand for molecular imaging
- Synthesis, radiolabeling and quality control of 111In-DOTA-bevacizumab for radioimmunoscintigraphy of VEGF receptors
- Isolation of hydroxytyrosol from olive leaves extract, radioiodination and investigation of bioaffinity using in vivo/in vitro methods
- Gold-coated lanthanide phosphate nanoparticles for an 225Ac in vivo alpha generator
- Interferences in instrumental neutron activation analysis by threshold reactions and uranium fission for miniature neutron source reactor