P. M. Prajapati

Fission Product Yield in the Neutron-Induced Fission of 232Th with Average Energies of 5.42, 7.75, and 10.09 MeV

Abstract The yields of various fission products in the neutron-induced fission of 232Th have been determined a using recoil catcher and off-line gamma-ray spectrometric technique with flux-averaged energies of 5.42, 7.75, and 10.09 MeV. The neutrons were generated using the 7Li(p,n) reaction at the BARC-TIFR [Bhabha Atomic Research Centre–Tata Institute of Fundamental Research] Pelletron facility, Mumbai, India. The fission product–yield data in the 10.09-MeV neutron-induced fission of 232Th are determined for the first time. The yields of the different fission products in the neutron-induced fission of 232Th with flux-averaged energies of 5.42 and 7.75 MeV from the present work have been compared with similar data of comparable neutron energy from the literature and are found to be in good agreement. The effect of nuclear structure on fission product yields as a function of neutron energy has been examined.

Measurement of Neutron-Induced Reaction Cross Sections in Zirconium Isotopes at Thermal, 2.45 MeV and 9.85 MeV Energies

Abstract The 94Zr(n,γ)95Zr and 90Zr(n,p)90Ym reaction cross sections were measured at neutron energies En of 2.45 MeV and 9.85 ± 0.38 MeV (average) using an activation and off-line gamma-ray spectrometric technique. In addition to these, the thermal neutron capture cross sections of 94Zr(n,γ)95Zr and 96Zr(n,γ)97Zr were also measured using the same technique. The experimentally measured neutron cross-section data were compared with the latest available evaluated nuclear data libraries from ENDF/B-VII, JENDL 4.0, and TENDL 2010.

Photo-neutron cross-section of 96Zr using bremsstrahlung radiation with end point energies of 10 and 12.5 MeV

Abstract 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.

Measurement of the 238 U(n,γ) 239 U and 238 U(n,2n) 237 U Reaction Cross Sections Using a Neutron Activation Technique at Neutron Energies of 8.04 and 11.90 MeV

Abstract The (n,γ) and (n,2n) capture cross sections of 238U have been measured at neutron energies of 8.04 ± 0.30 and 11.90 ± 0.35 MeV from the 7Li(p,n) reaction using an activation and off-line gamma-ray spectrometric technique. The experimentally determined 238U(n,γ) and 238U(n,2n) reaction cross sections were compared with the evaluated data of ENDF/B-VII.0, JENDL-4.0, JEFF-3.1/A, and CENDL-3.1. The experimental values were found to be in agreement with the evaluated value based on ENDF/B-VII.0, JENDL-4.0, and JEFF-3.1/A but not with CENDL-3.1. The present measurement has been compared with literature data in a wide range of neutron energies. The 238U(n,γ)239U and 238U(n,2n)237U reaction cross sections were also calculated theoretically using the TALYS 1.4 computer code and compared with the experimental data.