TAILIEUCHUNG - Báo cáo " Study on Monte-Carlo calculation of peak efficiencies of the superpure Hp Ge detector (Gmx) in environmental gamma spectrometry with using MCNP4C2 "

Monte-Carlo modeling allows calculating the detector efficiency in gamma spectrometry of environmental samples with taking into consideration both the photon selfabsorption in sample itself and absorption in all other materials between the sample and the detector’s active part. In this paper, the peak efficiencies of the Hp Ge detector (GMX) for gammas at various energies (emitted isotropically from the standard disk source and volumetric source - environmental sample, in which the different radionuclides are present) . | VNU Journal of Science Mathematics - Physics 23 2007 99-104 Study on Monte-Carlo calculation of peak efficiencies of the superpure Hp Ge detector Gmx in environmental gamma spectrometry with using MCNP4C2 Le Van Ngoc Nguyen Thi Thanh Huyen Nguyen Hao Quang Institute of Nuclear Science and Techniques . Box 5T-160 Hoang Quoc Viet Cau Giay Hanoi Vietnam Received 3 August 2007 received in revised form 17 October 2007 Abstract. Monte-Carlo modeling allows calculating the detector efficiency in gamma spectrometry of environmental samples with taking into consideration both the photon selfabsorption in sample itself and absorption in all other materials between the sample and the detector s active part. In this paper the peak efficiencies of the Hp Ge detector GMX for gammas at various energies emitted isotropically from the standard disk source and volumetric source - environmental sample in which the different radionuclides are present are calculated based on MCNP4C2-Monte-Carlo multi-purpose radiation transport code system developed in the Los-Alamos laboratory . The obtained calculating results are compared with the experimentally measured data and a good agreement between them is shown out. 1. Introduction Radioactive gamma sources which are often encountered in practice are in different forms from tiny specks of contaminants to sources spread over a surface as in a swipe test or a volume of source as in a sample contained in a vial and etc. In reactor environments these gamma sources are found not just in the reactor core but also elsewhere like in the spent fuel working area of the operators and so on. In all these cases gamma counting is needed for control and monitoring and for such a purpose one needs to know the detector efficiency correctly 1 2 . The detector efficiency is often measured experimentally with using a standard source. However for the decrease of experimental costs in the analysis of samples especially environmental ones one can specify .

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