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Mass distribution in the bremsstrahlung-induced fission of 232Th, 238U and 240Pu
Abstract The yields of various fission products in the 10 MeV bremsstrahlung-induced fission of 232Th, 238U and 240Pu were determined using a recoil catcher and off-line γ-ray spectrometricExpand
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Measurement of the 232Th(n, γ)233Th and 232Th(n, 2n)231Th reaction cross-sections at neutron energies of 8.04 ± 0.30 and 11.90 ± 0.35 MeV
Abstract The 232 Th(n, γ) 233 Th and 232 Th(n, 2n) 231 Th reaction cross-sections have been determined for the first time at average neutron energies of 8.04 ± 0.30 MeV and 11.90 ± 0.35 MeV usingExpand
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Measurement of the neutron capture cross-section of 232Th using the neutron activation technique
Abstract.The 232Th(n,$ \gamma$) reaction cross-section at average neutron energies of 3.7±0.3 MeV and 9.85±0.38 MeV from the 7Li(p, n) reaction has been determined for the first time using activationExpand
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Measurement of the neutron capture cross-sections of 232Th at 5.9 MeV and 15.5 MeV
Abstract.The 232Th(n, γ)233Th reaction cross-section has been determined for the first time using an activation and off-line γ-ray spectrometric technique at average neutron energies of 5.9 ± 0.6 MeVExpand
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Attenuation correction factors for cylindrical, disc and box geometry
In the present study, attenuation correction factors have been experimentally determined for samples having cylindrical, disc and box geometry and compared with the attenuation correction factorsExpand
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Neutron induced reaction cross-section of 232Th and 238U at the neutron energies of 2.45 and 14.8 MeV
For 232Th and 238U, 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 andExpand
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Standard-less analysis of Zircaloy clad samples by an instrumental neutron activation method
Abstract A non-destructive method for analysis of irregular shape and size samples of Zircaloy has been developed using the recently standardized k0-based internal mono standard instrumental neutronExpand
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A simple numerical method for gamma-ray self-attenuation correction for samples of common geometries
Abstract A simple numerical approach has been used to calculate attenuation correction factors for homogeneous samples of cylindrical, box-shaped and spherical geometries. The method involves theExpand
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Coincidence summing corrections for a clover detector
Abstract The true coincidence summing effect on the full energy peak efficiency calibration of a clover HPGe detector for point sources has been determined as a function of sample-to-detectorExpand
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Photo-neutron reaction cross-section for 93Nb in the end-point bremsstrahlung energies of 12–16 and 45–70 MeV
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 theExpand
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