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</script>Neutron-induced Fission Cross Section of 240,242Pu
Neutron-induced Fission Cross Section of 240,242Pu
A sensitivity analysis for the new generation of fast reactors [Salvatores (2008)] has shown the importance of improved cross section data for several actinides. Among them, the240,242Pu(n,f) cross sections require an accuracy improvement to 1-3% and 3-5%, respectively, from the current level of 6% and 20%. At the Van de Graaff facility of the Institute for Reference Materials and Measurements (JRC-IRMM) the fission cross section of the two isotopes was measured relative to two secondary standard reactions,237Np(n,f) and238U(n,f), using a twin Frisch-grid ionization chamber. The secondary standard reactions were benchmarked through measurements against the primary standard reaction235U(n,f) in the same geometry. Sample masses were determined by means of low-geometry alpha counting or/and a 2p Frisch-grid ionization chamber, with an uncertainty lower than 2%. The neutron flux and the impact of scattering from material between source and target was examined, the largest effect having been found in cross section ratio measurements between a fissile and a fertile isotope. Our240,242Pu(n,f) cross sections are in agreement with previous experimental results and slightly lower than present evaluations. In case of the242Pu(n,f) reaction no evidence for a resonance at En=1.1 MeV was found.
- Joint Research Center Belgium
- Universitat Politècnica de Catalunya Spain
- European Union Belgium
- Directorate-General Joint Research Centre Belgium
- European Commission Belgium
Ionization, Neutron detectors, 242Pu(n,f), f), Physics and Astronomy(all), 240Pu(n,f), Fissió nuclear, Actinides, Isotopes, 238U(n,f), 242Pu(n, :Energies::Energia nuclear [Àrees temàtiques de la UPC], Neutrons, 240Pu(n, Ionization chambers, Gamma rays, Nuclear energy, 237Np(n, Àrees temàtiques de la UPC::Energies::Energia nuclear, Fast reactors, Energia nuclear, neutron-induced fission cross section, Neutron-induced fission, 237Np(n,f), Sensitivity analysis, 238U(n
Ionization, Neutron detectors, 242Pu(n,f), f), Physics and Astronomy(all), 240Pu(n,f), Fissió nuclear, Actinides, Isotopes, 238U(n,f), 242Pu(n, :Energies::Energia nuclear [Àrees temàtiques de la UPC], Neutrons, 240Pu(n, Ionization chambers, Gamma rays, Nuclear energy, 237Np(n, Àrees temàtiques de la UPC::Energies::Energia nuclear, Fast reactors, Energia nuclear, neutron-induced fission cross section, Neutron-induced fission, 237Np(n,f), Sensitivity analysis, 238U(n
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