Neutron multiplicities of /sup 252/Cf and the fissile nuclei. Final report
James Richard Smith, S.D. Reeder, R.J. Gehrke
Abstract
James Richard Smith, S.D. Reeder, R.J. Gehrke
Abstract
The absolute value of anti nu, the average number of fission neutrons emitted per fission event, has been measured for the nuclear standard /sup 252/Cf, using the manganese bath technique. The fission rate of the /sup 252/Cf source was determined by observing coincindences between neutron and fission events. The neutron yield of the source was measured by use of a cablibrated manganese bath. The value obtained was anti nu = 3.767 +- 0.010 neutrons per fission. In a further study of neutron multiplicities the manganese bath measurements of eta, the average number of fission neutrons produced per neutron absorbed in a fissile nucleus, were reanalyzed using estimates of manganese bath systematic effects consistent with those used in the analysis of the /sup 252/Cf anti nu data. Part 3 of the report is a reanalysis of relative eta measurements made with a small manganese bath at a few energy points between 0.06 and 0.026 eV, for the nuclei /sup 233/U, /sup 235/U, /sup 239/Pu and /sup 241/Pu. Part 4 describes a corrected analysis of total cross section measurements for /sup 241/Pu, in the neutron energy interval 0.0005 to 0.10 eV. 70 references.
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The absolute value of anti nu, the average number of fission neutrons emitted per fission event, has been measured for the nuclear standard /sup 252/Cf, using the manganese bath technique. The fission rate of the /sup 252/Cf source was determined by observing coincindences between neutron and fission events. The neutron yield of the source was measured by use of a cablibrated manganese bath. The value obtained was anti nu = 3.767 +- 0.010 neutrons per fission. In a further study of neutron multiplicities the manganese bath measurements of eta, the average number of fission neutrons produced per neutron absorbed in a fissile nucleus, were reanalyzed using estimates of manganese bath systematic effects consistent with those used in the analysis of the /sup 252/Cf anti nu data. Part 3 of the report is a reanalysis of relative eta measurements made with a small manganese bath at a few energy points between 0.06 and 0.026 eV, for the nuclei /sup 233/U, /sup 235/U, /sup 239/Pu and /sup 241/Pu. Part 4 describes a corrected analysis of total cross section measurements for /sup 241/Pu, in the neutron energy interval 0.0005 to 0.10 eV. 70 references.
Key concepts: Fissile material, Neutron, Fission, Nuclear physics, Delayed neutron, Manganese, Radiochemistry, Physics