DIFFERENTIAL CROSS-SECTIONS FOR THE U(n,xn) REACTION AT A NEUTRON ENERGY OF 14.3 MeV

Authors & Affiliations

Devkin B.V., Kobozev M.G., Lychagin A.A., Simakov S.P., Talalaev V.A.
Institute of Physics and Power Engineering, Obninsk, Russia

Abstract

The results of measurements of double-differential neutron emission cross-sections for the U(n,xn) reaction at 14.3 ± 0.1 MeV incident neutron energy are given. The measurements were made using the time-of-flight technique with the IPPE’s KG-0.3 pulsed neutron generator. The paper describes the experimental set-up and the results of the measurements and contains comparisons with data from other experiments and the ENDF-B6 and ENDL-85 evaluated data libraries.

Keywords
energy and angular distributions of neutrons, induced fission process, Evaluated Nuclear Data Library, differential cross section for neutron emission, pulsed neutron generator KG-0.3

Article Text (PDF, in English, Translated by IAEA)

References

UDC 539.17

Problems of Atomic Science and Technology. Series: Nuclear Constants", issue 2, 1999