TY - JOUR
T1 - Efficiency calculation and coincidence summing correction for germanium detectors by Monte Carlo simulation
AU - Wang, Zhonglu
AU - Kahn, Bernd
AU - Valentine, John D.
N1 - Funding Information:
Manuscript received November 28, 2001; revised February 27, 2002. This work was supported in part by the China Scholarship Council. Z. Wang is with the Nuclear and Radiological Engineering Program, Woodruff School of Mechanical Engineering, Georgia Institute of Technology, Atlanta, GA 30332 USA (e-mail: [email protected]). B. Kahn is with the Environmental Resources Center, Georgia Institute of Technology, Atlanta, GA 30332 USA (e-mail: [email protected]). J. D. Valentine was with the Nuclear and Radiological Engineering Program, Woodruff School of Mechanical Engineering, Georgia Institute of Technology, Atlanta, GA 30332 USA. He is currently with Lawrence Livermore National Laboratory, Livermore, CA 94550 USA (e-mail: [email protected]). Digital Object Identifier 10.1109/TNS.2002.801679
PY - 2002/8
Y1 - 2002/8
N2 - A method is presented for efficiency calculation and coincidence-summing correction of high-purity germanium (HPGe) detector spectra by using Monte Carlo N-particle transport (MCNP) code. This technique will be used in the efficiency calibration of HPGe detectors to reduce the number of standard sources to be prepared. Modeling of the detector geometry is described in detail, and differences between the simulated and measured spectra are discussed. Standard point sources traceable to the National Institute for Science and Technology were used to measure the full-energy peak and total efficiencies. The simulated full-energy peak efficiency for noncoincidence 137Cs gamma rays agreed with the measured value to within 2%, but the simulated total efficiency is about 8% lower than the measured value for 662 keV. A 60Co point source was placed in five positions above along the center line of the detector from 0.6 to 14.2 cm. For the 1173- and 1332-keV gamma rays from 60Co, their spectra were simulated using MCNP separately. Subsequently, these spectra were combined according to their coincidence relationship to form the simulated 60Co spectrum. 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.
AB - A method is presented for efficiency calculation and coincidence-summing correction of high-purity germanium (HPGe) detector spectra by using Monte Carlo N-particle transport (MCNP) code. This technique will be used in the efficiency calibration of HPGe detectors to reduce the number of standard sources to be prepared. Modeling of the detector geometry is described in detail, and differences between the simulated and measured spectra are discussed. Standard point sources traceable to the National Institute for Science and Technology were used to measure the full-energy peak and total efficiencies. The simulated full-energy peak efficiency for noncoincidence 137Cs gamma rays agreed with the measured value to within 2%, but the simulated total efficiency is about 8% lower than the measured value for 662 keV. A 60Co point source was placed in five positions above along the center line of the detector from 0.6 to 14.2 cm. For the 1173- and 1332-keV gamma rays from 60Co, their spectra were simulated using MCNP separately. Subsequently, these spectra were combined according to their coincidence relationship to form the simulated 60Co spectrum. 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.
UR - http://www.scopus.com/inward/record.url?scp=0036703266&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=0036703266&partnerID=8YFLogxK
U2 - 10.1109/TNS.2002.801679
DO - 10.1109/TNS.2002.801679
M3 - Article
AN - SCOPUS:0036703266
SN - 0018-9499
VL - 49 I
SP - 1925
EP - 1931
JO - IEEE Transactions on Nuclear Science
JF - IEEE Transactions on Nuclear Science
IS - 4
ER -