Measurement of the neutron capture cross-section of [sup.238]U using the neutron activation technique

The [sup.238]U(n, γ)[sup.239]U reaction cross-section at average neutron energy of 3.7 ± 0.3 MeV from the [sup.7]Li(p, n)[sup.7]Be reaction has been determined using activation and off-line y-ray spectrometric technique. The [sup.238]U(n, γ)[sup.239]U and [sup.238]U(n, 2n)[sup.237]U reaction cross-sections at average neutron energy of 9.85 ± 0.38 MeV from the same [sup.7]Li(p, n)[sup.7]Be reaction have been also determined using the above technique. The experimentally determined [sup.238]U(n, γ)[sup.239]U and [sup.238]U(n, 2n)[sup.237U 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 [sup.238]U(n, γ)[sup.239]U and [sup.238]U(n, 2n)[sup.237]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. Keywords [sup.238]U(n, γ)[sup.239]U and [sup.238]U(n, 2n)[sup.237]U reaction cross-sections * [sup.7]Li(p, n)[sup.7]Be reaction * Average neutron energy * [E.sub.n] = 3.7 ± 0.3 MeV and 9.85 ± 0.38 MeV * Off-line γ-ray spectrometric technique * TALYS calculation