Geant4 and MCNPX simulations of thermal neutron detection with planar silicon detectors

C. Guardiola; K. Amgarou; F. García; C. Fleta; D. Quirion; M. Lozano

doi:https://doi.org/10.1088/1748-0221/6/09/T09001

Geant4 and MCNPX simulations of thermal neutron detection with planar silicon detectors

C. Guardiola, K. Amgarou, F. García, C. Fleta, D. Quirion, M. Lozano

Department of Physics

Research output: Contribution to journal › Article › Research › peer-review

19 Citations (Scopus)

Abstract

We used Geant4 and MCNPX codes to evaluate the detection efficiency of planar silicon detectors coupled to different Boron-based converters with varied compositions and thicknesses that detect thermal neutrons via the 10B(n,α)7Li nuclear reaction. Few studies about the thermal neutron transport in Geant4 have been reported so far and it is becoming increasingly difficult to ignore its discrepancies with MCNPX in this neutron energy range. In the thermal energy range, Geant4 shows high discrepancies with MCNPX giving a maximum efficiency of about 3.3% in the 10B case whereas that obtained with MCNPX was 5%. Disagreements obtained between both codes in this energy range are analyzed and discussed. © 2011 IOP Publishing Ltd and SISSA.

Original language	English
Article number	T09001
Journal	Journal of Instrumentation
Volume	6
DOIs	https://doi.org/10.1088/1748-0221/6/09/T09001
Publication status	Published - 1 Sep 2011

Keywords

Detector modelling and simulations I (interaction of radiation with matter, interaction of photons with matter, interaction of hadrons with matter, etc)
Neutron detectors (cold, thermal, fast neutrons)
Simulation methods and programs
Solid state detectors

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title = "Geant4 and MCNPX simulations of thermal neutron detection with planar silicon detectors",

abstract = "We used Geant4 and MCNPX codes to evaluate the detection efficiency of planar silicon detectors coupled to different Boron-based converters with varied compositions and thicknesses that detect thermal neutrons via the 10B(n,α)7Li nuclear reaction. Few studies about the thermal neutron transport in Geant4 have been reported so far and it is becoming increasingly difficult to ignore its discrepancies with MCNPX in this neutron energy range. In the thermal energy range, Geant4 shows high discrepancies with MCNPX giving a maximum efficiency of about 3.3% in the 10B case whereas that obtained with MCNPX was 5%. Disagreements obtained between both codes in this energy range are analyzed and discussed. {\textcopyright} 2011 IOP Publishing Ltd and SISSA.",

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year = "2011",

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T1 - Geant4 and MCNPX simulations of thermal neutron detection with planar silicon detectors

AU - Guardiola, C.

AU - Amgarou, K.

AU - García, F.

AU - Fleta, C.

AU - Quirion, D.

AU - Lozano, M.

PY - 2011/9/1

Y1 - 2011/9/1

N2 - We used Geant4 and MCNPX codes to evaluate the detection efficiency of planar silicon detectors coupled to different Boron-based converters with varied compositions and thicknesses that detect thermal neutrons via the 10B(n,α)7Li nuclear reaction. Few studies about the thermal neutron transport in Geant4 have been reported so far and it is becoming increasingly difficult to ignore its discrepancies with MCNPX in this neutron energy range. In the thermal energy range, Geant4 shows high discrepancies with MCNPX giving a maximum efficiency of about 3.3% in the 10B case whereas that obtained with MCNPX was 5%. Disagreements obtained between both codes in this energy range are analyzed and discussed. © 2011 IOP Publishing Ltd and SISSA.

AB - We used Geant4 and MCNPX codes to evaluate the detection efficiency of planar silicon detectors coupled to different Boron-based converters with varied compositions and thicknesses that detect thermal neutrons via the 10B(n,α)7Li nuclear reaction. Few studies about the thermal neutron transport in Geant4 have been reported so far and it is becoming increasingly difficult to ignore its discrepancies with MCNPX in this neutron energy range. In the thermal energy range, Geant4 shows high discrepancies with MCNPX giving a maximum efficiency of about 3.3% in the 10B case whereas that obtained with MCNPX was 5%. Disagreements obtained between both codes in this energy range are analyzed and discussed. © 2011 IOP Publishing Ltd and SISSA.

KW - Detector modelling and simulations I (interaction of radiation with matter, interaction of photons with matter, interaction of hadrons with matter, etc)

KW - Neutron detectors (cold, thermal, fast neutrons)

KW - Simulation methods and programs

KW - Solid state detectors

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DO - https://doi.org/10.1088/1748-0221/6/09/T09001

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JO - Journal of Instrumentation

JF - Journal of Instrumentation

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