Neutron multiplicities of /sup 252/Cf and the fissile nuclei. Final report
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.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- OSTI ID:
- 6846536
- Report Number(s):
- EPRI-NP-3436; ON: TI84920322
- Country of Publication:
- United States
- Language:
- English
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Measurements of the energy dependence of prompt neutron emission from /sup 233/U, /sup 235/U, /sup 239/Pu, and /sup 241/Pu for E /SUB n/ = 0. 005 to 10 eV relative to emission from spontaneous fission of /sup 252/Cf
Measurements of the energy dependence of prompt neutron emission from /sup 233/U, /sup 235/U, and /sup 239/Pu for E/sub n/ = 0. 0005 to 10 MeV relative to emission from spontaneous fission of /sup 252/Cf
Related Subjects
CALIFORNIUM 252
SPONTANEOUS FISSION
FISSION NEUTRONS
MULTIPLICITY
NEUTRON REACTIONS
FISSION
PLUTONIUM 239 TARGET
PLUTONIUM 241 TARGET
URANIUM 233 TARGET
URANIUM 235 TARGET
ACTIVATION DETECTORS
ANGULAR CORRELATION
CAPTURE-TO-FISSION RATIO
COINCIDENCE METHODS
CORRECTIONS
EXPERIMENTAL DATA
MANGANESE
MEASURING METHODS
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BARYON REACTIONS
BARYONS
CALIFORNIUM ISOTOPES
CORRELATIONS
COUNTING TECHNIQUES
DATA
DECAY
ELEMENTARY PARTICLES
ELEMENTS
EVEN-EVEN NUCLEI
FERMIONS
HADRON REACTIONS
HADRONS
HEAVY NUCLEI
INFORMATION
ISOTOPES
MEASURING INSTRUMENTS
METALS
NEUTRON DETECTORS
NEUTRONS
NUCLEAR REACTIONS
NUCLEI
NUCLEON REACTIONS
NUCLEONS
NUMERICAL DATA
RADIATION DETECTORS
RADIOISOTOPES
TARGETS
TRANSITION ELEMENTS
YEARS LIVING RADIOISOTOPES
652026* - Nuclear Properties & Reactions
A=220 & above
Experimental- Spontaneous & Induced Fission- (-1987)