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Neutron multiplicities of /sup 252/Cf and the fissile nuclei. Final report

James Richard Smith, S.D. Reeder, R.J. Gehrke

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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.

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Available 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.

Key concepts: Fissile material, Neutron, Fission, Nuclear physics, Delayed neutron, Manganese, Radiochemistry, Physics

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