Efficiency calculation and coincidence summing correction of a germanium detector by Monte-Carlo simulation

Zhonglu Wang, Bernd Kahn, John D. Valentine

Research output: Contribution to conferencePaper

1 Citation (Scopus)

Abstract

A method of efficiency calculation and coincidence-summing correction of a germanium detector by using MCNP code is presented. Modeling of the detector geometry is described in detail and differences between the simulated and measured spectra are discussed. Standard point sources traceable to NIST were used to measure the full-energy peak and total efficiencies. A 60Co point source was placed in five positions above the detector from 0.6 cm to 14.2 cm. For the 1173 keV and 1332 keV gamma rays from 60Co, their spectra were simulated by MCNP separately. Subsequently, these spectra were combined according to their coincidence relationship to form the simulated 60Co spectrum. Cs-137 was used to compare a simple measured spectrum with the MCNP simulation. The simulated full energy peak efficiency for non-coincidence gamma rays agreed with the measured value to within 2%, but the simulated total efficiency is about 8% lower for 662 keV. The calculated coincidence summing factors for 1173 and 1332 keV are about 3% lower than the measured values at the closest geometry for a point source due to the underestimation of the total efficiency. This technique will be used in the efficiency calibration of Ge detectors to avoid the difficulties of preparing standard sources.

Original languageEnglish (US)
Pages1037-1041
Number of pages5
StatePublished - Dec 1 2001
Event2001 IEEE Nuclear Science Symposium Conference Record - San Diege, CA, United States
Duration: Nov 4 2001Nov 10 2001

Other

Other2001 IEEE Nuclear Science Symposium Conference Record
CountryUnited States
CitySan Diege, CA
Period11/4/0111/10/01

Fingerprint

Germanium
Detectors
Gamma rays
Geometry
Monte Carlo simulation
Calibration

All Science Journal Classification (ASJC) codes

  • Computer Vision and Pattern Recognition
  • Industrial and Manufacturing Engineering

Cite this

Wang, Z., Kahn, B., & Valentine, J. D. (2001). Efficiency calculation and coincidence summing correction of a germanium detector by Monte-Carlo simulation. 1037-1041. Paper presented at 2001 IEEE Nuclear Science Symposium Conference Record, San Diege, CA, United States.
Wang, Zhonglu ; Kahn, Bernd ; Valentine, John D. / Efficiency calculation and coincidence summing correction of a germanium detector by Monte-Carlo simulation. Paper presented at 2001 IEEE Nuclear Science Symposium Conference Record, San Diege, CA, United States.5 p.
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Wang, Z, Kahn, B & Valentine, JD 2001, 'Efficiency calculation and coincidence summing correction of a germanium detector by Monte-Carlo simulation', Paper presented at 2001 IEEE Nuclear Science Symposium Conference Record, San Diege, CA, United States, 11/4/01 - 11/10/01 pp. 1037-1041.

Efficiency calculation and coincidence summing correction of a germanium detector by Monte-Carlo simulation. / Wang, Zhonglu; Kahn, Bernd; Valentine, John D.

2001. 1037-1041 Paper presented at 2001 IEEE Nuclear Science Symposium Conference Record, San Diege, CA, United States.

Research output: Contribution to conferencePaper

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N2 - A method of efficiency calculation and coincidence-summing correction of a germanium detector by using MCNP code is presented. Modeling of the detector geometry is described in detail and differences between the simulated and measured spectra are discussed. Standard point sources traceable to NIST were used to measure the full-energy peak and total efficiencies. A 60Co point source was placed in five positions above the detector from 0.6 cm to 14.2 cm. For the 1173 keV and 1332 keV gamma rays from 60Co, their spectra were simulated by MCNP separately. Subsequently, these spectra were combined according to their coincidence relationship to form the simulated 60Co spectrum. Cs-137 was used to compare a simple measured spectrum with the MCNP simulation. The simulated full energy peak efficiency for non-coincidence gamma rays agreed with the measured value to within 2%, but the simulated total efficiency is about 8% lower for 662 keV. The calculated coincidence summing factors for 1173 and 1332 keV are about 3% lower than the measured values at the closest geometry for a point source due to the underestimation of the total efficiency. This technique will be used in the efficiency calibration of Ge detectors to avoid the difficulties of preparing standard sources.

AB - A method of efficiency calculation and coincidence-summing correction of a germanium detector by using MCNP code is presented. Modeling of the detector geometry is described in detail and differences between the simulated and measured spectra are discussed. Standard point sources traceable to NIST were used to measure the full-energy peak and total efficiencies. A 60Co point source was placed in five positions above the detector from 0.6 cm to 14.2 cm. For the 1173 keV and 1332 keV gamma rays from 60Co, their spectra were simulated by MCNP separately. Subsequently, these spectra were combined according to their coincidence relationship to form the simulated 60Co spectrum. Cs-137 was used to compare a simple measured spectrum with the MCNP simulation. The simulated full energy peak efficiency for non-coincidence gamma rays agreed with the measured value to within 2%, but the simulated total efficiency is about 8% lower for 662 keV. The calculated coincidence summing factors for 1173 and 1332 keV are about 3% lower than the measured values at the closest geometry for a point source due to the underestimation of the total efficiency. This technique will be used in the efficiency calibration of Ge detectors to avoid the difficulties of preparing standard sources.

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Wang Z, Kahn B, Valentine JD. Efficiency calculation and coincidence summing correction of a germanium detector by Monte-Carlo simulation. 2001. Paper presented at 2001 IEEE Nuclear Science Symposium Conference Record, San Diege, CA, United States.