Journal of Radioanalytical and Nuclear Chemistry

, Volume 293, Issue 2, pp 469–478

Measurement of the neutron capture cross-section of 238U using the neutron activation technique

Authors

    • Radiochemistry DivisionBhabha Atomic Research Centre
  • S. V. Surayanarayana
    • Nuclear Physics DivisionBhabha Atomic Research Centre
  • V. K. Mulik
    • Department of PhysicsUniversity of Pune
  • P. M. Prajapati
    • Department of Physics, Faculty of ScienceThe M. S. University of Baroda
  • B. S. Shivashankar
    • Department of StatisticsManipal University
  • K. C. Jagadeesan
    • Radiopharmaceutical DivisionBhabha Atomic Research Centre
  • S. V. Thakare
    • Radiopharmaceutical DivisionBhabha Atomic Research Centre
  • D. Raj
    • Reactor Physics Design DivisionBhabha Atomic Research Centre
  • S. C. Sharma
    • Nuclear Physics DivisionBhabha Atomic Research Centre
  • P. V. Bhagwat
    • Nuclear Physics DivisionBhabha Atomic Research Centre
  • S. D. Dhole
    • Department of PhysicsUniversity of Pune
  • S. Ganesan
    • Reactor Physics Design DivisionBhabha Atomic Research Centre
  • V. N. Bhoraskar
    • Department of PhysicsUniversity of Pune
  • A. Goswami
    • Radiochemistry DivisionBhabha Atomic Research Centre
Article

DOI: 10.1007/s10967-012-1815-x

Cite this article as:
Naik, H., Surayanarayana, S.V., Mulik, V.K. et al. J Radioanal Nucl Chem (2012) 293: 469. doi:10.1007/s10967-012-1815-x

Abstract

The 238U(n, γ)239U reaction cross-section at average neutron energy of 3.7 ± 0.3 MeV from the 7Li(p, n)7Be reaction has been determined using activation and off-line γ-ray spectrometric technique. The 238U(n, γ)239U and 238U(n, 2n)237U reaction cross-sections at average neutron energy of 9.85 ± 0.38 MeV from the same 7Li(p, n)7Be reaction have been also determined using the above technique. The experimentally determined 238U(n, γ)239U and 238U(n, 2n)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 238U(n, γ)239U and 238U(n, 2n)237U 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

238U(n, γ)239U and 238U(n, 2n)237U reaction cross-sections7Li(p, n)7Be reactionAverage neutron energyEn = 3.7 ± 0.3 MeV and 9.85 ± 0.38 MeVOff-line γ-ray spectrometric techniqueTALYS calculation

Copyright information

© Akadémiai Kiadó, Budapest, Hungary 2012