Monte Carlo characterisation of a Compton suppressed broad-energy HPGe detector

AbstractIn-situ measurement of marine sediment radioactivity does not destroy the stratification of radionuclides in the sediment. We develop a novel seabed sediment radioactive measurement technique using a High Purity Germanium (HPGe) detector. The overall measurement system is designed, and the detector energy calibration is performed. The efficiency is calculated based on Monte Carlo simulations using the MCNP5 code. We compared the efficiency and energy resolution with the NaI(Tl) detection through experiments. NaI(Tl) detection is incapable of identifying the 137Cs artificial nuclides in seabed sediments due to the energy resolution limit. Hence, underwater HPGe detection is utilized due to its high energy resolution, which enables the detection of artificial nuclides 137Cs. The proposed method is of great significance in evaluating marine radioactive pollution.

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Using lattice tools and unfolding methods for hpge detector efficiency simulation with the Monte Carlo code MCNP5

Radiation Physics and Chemistry ◽

10.1016/j.radphyschem.2015.01.027 ◽

2015 ◽

Vol 116 ◽

pp. 219-225 ◽

Cited By ~ 1

Author(s):

A. Querol ◽

S. Gallardo ◽

J. Ródenas ◽

G. Verdú

Keyword(s):

Monte Carlo ◽

Hpge Detector ◽

Monte Carlo Code ◽

Detector Efficiency

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The Generation of Few-Group Constants for Fast Reactor Analysis

Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors ◽

10.1115/icone24-60331 ◽

2016 ◽

Author(s):

Xianan Du ◽

Liangzhi Cao ◽

Youqi Zheng

Keyword(s):

Monte Carlo ◽

Cross Section ◽

Cross Sections ◽

Fast Reactor ◽

Monte Carlo Calculation ◽

Anisotropic Scattering ◽

Slowing Down ◽

Nodal Method ◽

Reactor Calculation ◽

Broad Energy

A way to generate the few-group cross sections for fast reactor calculation is presented in this paper. It is based on the three steps computational scheme. In the first step, the ultrafine method is used to solve the slowing down equation based on the ultrafine group cross section generated by NJOY. Optional 0D or 1D calculation is used to collapse energy group into broad energy groups. In the second step, the 2D RZ calculation using SN method is performed to obtain the space dependent neutron spectra to collapse broad energy groups into few groups. The anisotropic scattering is well handled by the direct SN calculation. Finally, the full core calculation is performed by using the 3D SN nodal method. The results are compared with continuous energy Monte-Carlo calculation. Both the cross section generated in the first step and the final keff in the last step are compared. The results match well between the three steps calculation and Monte-Carlo calculation.

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Derivation of an efficiency-calibration simulation for a well-type HPGe detector using the Monte Carlo approach and analytical techniques

Radiation Measurements ◽

10.1016/j.radmeas.2014.10.003 ◽

2015 ◽

Vol 73 ◽

pp. 36-45 ◽

Cited By ~ 10

Author(s):

E. Eren Belgin ◽

G.A. Aycik

Keyword(s):

Monte Carlo ◽

Hpge Detector ◽

Analytical Techniques ◽

Efficiency Calibration ◽

Monte Carlo Approach

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Monte Carlo based geometrical model for efficiency calculation of an n-type HPGe detector

Applied Radiation and Isotopes ◽

10.1016/j.apradiso.2010.06.018 ◽

2010 ◽

Vol 68 (12) ◽

pp. 2403-2408 ◽

Cited By ~ 24

Author(s):

Fatima Padilla Cabal ◽

Neivy Lopez-Pino ◽

Jose Luis Bernal-Castillo ◽

Yisel Martinez-Palenzuela ◽

Jimmy Aguilar-Mena ◽

...

Keyword(s):

Monte Carlo ◽

Hpge Detector ◽

Geometrical Model ◽

Efficiency Calculation

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Study on Variation of HPGE Detector Dead Layer Thickness and its Effect on the Measurements of the Detector Response and Samples Characterization Using Monte Carlo Simulation

Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory ◽

10.1115/icone26-82098 ◽

2018 ◽

Author(s):

K. Abd El Gawad ◽

Yushou Song

Keyword(s):

Monte Carlo ◽

Monte Carlo Method ◽

Layer Thickness ◽

Hpge Detector ◽

Dead Layer ◽

Nuclear Safeguards ◽

Detector Response ◽

Dead Layer Thickness ◽

235U Enrichment ◽

Good Agreement

The main objective of this work is to produce an optimal modeling for our aged Planar-HPGe detector using Monte Carlo method (MC). That optimization included the analysis of the germanium dead (inactive) layer thickness for our old detection system (planar-HPGe detector). DL is one of the important parameters needed in order to obtain the smallest discrepancy between simulated and experimental measurements of detector efficiency. Also, precise determination of 235U enrichment for UO2 samples which is necessary for purposes of nuclear materials verification in the field of nuclear safeguards. The thickness of Germanium dead layer (DL) can be vary by time as it is not well known due to the existence of a transition zone where photons are strongly attenuated and absorbed, that cannot contribute to the total photon energy absorption which causes a significant decrease in efficiency. Therefore, using data provided by manufacturers since long years (manufacture date) in the detector simulation model is not convenient. As a result, some strong discrepancies appear between measured and simulated efficiency, in addition to that non-accurate results for 235U enrichment determination. The Monte Carlo method applied to overcome this difficulty was to vary the thickness of dead layer step by step in simulation, a good agreement (minimum deviation) between estimated and experimental efficiency was reached when a suitable germanium dead layer thickness was chosen. Calculations and measurements were performed for radioactive nuclear material samples in the form of UO2 powder with different sizes and enrichments at different locations, under different gamma-lines emitted after a-decay of the 235U nuclei. Results indicated that a good agreement between simulated and measured efficiencies is obtained using a value for the germanium dead layer thickness approximately (2.45 mm) six in comparison with (0.389 mm) provided by the detector manufacturer.

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