Efficiency and resolution of germanium detectors as a function of energy and incident geometry

Keyser, Ronald M.; Hensley, W.K.

doi:10.1109/nssmic.2002.1239336

Cited by 6 publications

(7 citation statements)

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“…Such disagreement, also observed in other studies may be reduced by optimizing detector parameters [14], [15], [16], [17], [13], [18], and particularly the dead layer [19]. The two large discrepancies on the 444 keV and 564 keV photopeaks are probably due to a too low peak intensity and insufficient number of simulated particles.…”

Section: Third Studymentioning

confidence: 63%

Benchmark study of TRIPOLI-4 through experiment and MCNP codes

Michel

Coulon

Normand

et al. 2011

2011 2nd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and Their Applications

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Reliability on simulation results is essential in nuclear physics. Although MCNP5 and MCNPX are the world widely used 3D Monte Carlo radiation transport codes, alternative Monte Carlo simulation tools exist to simulate neutral and charged particles' interactions with matter. Therefore, benchmark are required in order to validate these simulation codes. For instance, TRIPOLI-4.7, developed at the French Alternative Energies and Atomic Energy Commission for neutron and photon transport, now also provides the user with a full feature electron-photon electromagnetic shower. Whereas the reliability of TRIPOLI-4.7 for neutron and photon transport has been validated yet, the new development regarding electron-photon matter interaction needs additional validation benchmarks. We will thus demonstrate how accurately TRIPOLI-4's "deposited spectrum" tally can simulate gamma spectrometry problems, compared to MCNP's "F8" tally. The experimental setup is based on an HPGe detector measuring the decay spectrum of an 152 Eu source. These results are then compared with those given by MCNPX 2.6d and TRIPOLI-4 codes. This paper deals with both the experimental aspect and simulation. We will demonstrate that TRIPOLI-4 is a potential alternative to both MCNPX and MCNP5 for gamma-electron interaction simulation.

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Section: Third Studymentioning

confidence: 63%

Benchmark study of TRIPOLI-4 through experiment and MCNP codes

Michel

Coulon

Normand

et al. 2011

2011 2nd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and Their Applications

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“…The measurements are made using a highly collimated low energy photon source. Each of the two measurements is made at differing angles so that the thickness of the dead layer can then be determined (Keyser and Hensley 2005). The difference between the two measurements is used to estimate the attenuation and thus the thickness of the dead layer.…”

Section: Angular Responsementioning

confidence: 99%

“…The detector crystal is 8.2 cm in diameter and 9.0 cm in height. The detector and its dead layer is from one of the MCNP models used in Keyser and Hensley's paper (Keyser and Hensley 2005). The model was obtained from the authors to use as an approximation of a detector.…”

Section: Angular Responsementioning

confidence: 99%

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A Numerical Method for the Calibration of in Situ Gamma Ray Spectroscopy Systems

Dewey¹,

Whetstone

Kearfott

2010

Health Physics

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High purity germanium in situ gamma ray spectroscopy systems are typically calibrated using pre-calculated tables and empirical formulas to estimate the response of a detector to an exponentially distributed source in a soil matrix. Although this method is effective, it has estimated uncertainties of 10-15%, is limited to only a restricted set of measurement scenarios, and the approach only applies to an exponentially distributed source. In addition, the only soil parameters that can be varied are density and moisture content, while soil attenuation properties are fixed. This paper presents a more flexible method for performing such calibrations. For this new method, a three- or four-dimensional analytical expression is derived that is a combination of a theoretical equation and experimentally measured data. Numerical methods are used to integrate this expression, which approximates the response of a detector to a large variety of source distributions within any soil, concrete, or other matrix. The calculation method is flexible enough to allow for the variation of multiple parameters, including media attenuation properties and the measurement geometry. The method could easily be adapted to horizontally non-uniform sources as well. Detector responses are calculated analytically and Monte Carlo radiation transport simulations are used to verify the results. Results indicate that the method adds an uncertainty of only approximately 5% to the other uncertainties typically associated with the calibration of a detector system.

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“…By way of examples, a few studies on this topic are listed in Refs. [1][2][3][4][5][6][7][8][9][10][11][12][13][14], except [12] concern P-type detectors. In most of these studies, substantial discrepancies between calculated and experimental data are observed.…”

Section: Introductionmentioning

confidence: 99%