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Detection System Characteristics Using 252Cf Ionization Chambers

Conference ·
OSTI ID:6732383
 [1];  [1];  [1];  [1]
  1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Because the number of neutrons and gamma rays and the energy spectrum of particles from spontaneous fission are well characterized for 252Cf, it can be used as a timed source of fission neutrons and gamma rays. The first such usage incorporated a 252Cf source into gas scintillators. This paper describes a timed source of neutrons and gamma rays made by depositing 252Cf on one electrode of a parallel plate ionization chamber that can then be used for determining detection-system characteristics. The emission time of neutrons from spontaneous fission has also been determined by recording the emission time of prompt gamma rays from a 252Cf source (not incorporated into a detector) adjacent to the surface of a solid or liquid scintillator. This well characterized source of neutrons can thus be used as a randomly pulsed source for a variety of applications. This paper illustrates the use of this type of source to determine the time resolution of detection systems, the efficiency for detection of neutrons between 0.5 and 5 MeV, the effectiveness of pulse shape discrimination systems, and the overall efficiency for detection of prompt fission gamma rays.
Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
DOE Contract Number:
AC05-84OR21400
OSTI ID:
6732383
Report Number(s):
CONF-900563-9; ON: DE90011702
Country of Publication:
United States
Language:
English

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