Absolute measurement of anti. nu. /sub p/ for /sup 252/Cf using the ORNL large liquid scintillator neutron detector

Technical Report · Sat Aug 01 00:00:00 EDT 1981

DOI:https://doi.org/10.2172/6223355· OSTI ID:6223355

Spencer, R. R.; Gwin, R.; Ingle, R.

The ORNL large liquid scintillator detector was used in a precise determination of anti ..nu../sub p/, the number of neutrons emitted promptly, for spontaneous fission of /sup 252/Cf. Measurements of the detector efficiency over a broad energy region were made by means of a proton-recoil technique employing the ORELA white neutron source. Monte Carlo calculation of the detector efficiency for a spectrum representative of /sup 252/Cf fission neutrons was calibrated with these elaborate measurements. The unusually flat response of the neutron detector resulted in elimination of several known sources of error. Experimental measurement was coupled with calculational methods to correct for other known errors. These measurements lead to an unusually small estimated uncertainty of 0.2% in the value obtained, anti ..nu../sub p/ = 3.773 +- 0.007.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6223355
• Report Number(s): ORNL/TM-7940; ON: DE81030228; TRN: 81-016311
• Country of Publication: United States
• Language: English

Related Subjects

73 NUCLEAR PHYSICS AND RADIATION PHYSICS
CALIFORNIUM 252
SPONTANEOUS FISSION
LIQUID SCINTILLATION DETECTORS
EFFICIENCY
PROMPT NEUTRONS
CALIBRATION
DATA ACQUISITION SYSTEMS
ERRORS
EXPERIMENTAL DATA
MEASURING METHODS
MONTE CARLO METHOD
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BARYONS
CALIFORNIUM ISOTOPES
DATA
DECAY
ELEMENTARY PARTICLES
EVEN-EVEN NUCLEI
FERMIONS
FISSION
FISSION NEUTRONS
HADRONS
HEAVY NUCLEI
INFORMATION
ISOTOPES
MEASURING INSTRUMENTS
NEUTRONS
NUCLEAR REACTIONS
NUCLEI
NUCLEONS
NUMERICAL DATA
RADIATION DETECTORS
RADIOISOTOPES
SCINTILLATION COUNTERS
YEARS LIVING RADIOISOTOPES
652026* - Nuclear Properties & Reactions
A=220 & above
Experimental- Spontaneous & Induced Fission- (-1987)