scholarly journals Integration of the differential evolution algorithm and the Monte Carlo code to create a spectrometric detector model

2022 ◽  
Vol 2155 (1) ◽  
pp. 012020
Author(s):  
I V Prozorova
Keyword(s):  
Monte Carlo ◽  
Standard Procedure ◽  
Differential Evolution Algorithm ◽  
Germanium Detector ◽  
Cost Effective ◽  
Monte Carlo Code ◽  
High Purity Germanium ◽  
The Monte Carlo Method ◽  
Evolution Algorithm ◽  
Detector Model

Abstract A standard procedure for characterizing the high-purity germanium detector (HPGe), manufactured by Canberra Industries Inc [1], is performed directly by the company using patented methods. However, the procedure is usually expensive and must be repeated because the characteristics of the HPGe crystal change over time. In this work, the principles of a technique are developed for use in obtaining and optimizing the detector characteristics based on a cost-effective procedure in a standard research laboratory. The technique requires that the detector geometric parameters are determined with maximum accuracy by the Monte Carlo method [2] in parallel with the optimization based on evolutionary algorithms. The development of this approach facilitates modeling of the HPGe detector as a standardized procedure. The results will be also beneficial in the development of gamma spectrometers and/or their calibrations before routine measurements.

Monte Carlo simulation of gamma-ray interactions in an over-square high-purity germanium detector for in-vivo measurements

2016 ◽  
Vol 44 ◽  
pp. 1660225
Author(s):  
Mirela Angela Saizu
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Method ◽  
High Purity ◽  
Hpge Detector ◽  
Germanium Detector ◽  
Efficiency Calibration ◽  
Gamma Energy ◽  
High Purity Germanium ◽  
The Monte Carlo Method

The developments of high-purity germanium detectors match very well the requirements of the in-vivo human body measurements regarding the gamma energy ranges of the radionuclides intended to be measured, the shape of the extended radioactive sources, and the measurement geometries. The Whole Body Counter (WBC) from IFIN-HH is based on an “over-square” high-purity germanium detector (HPGe) to perform accurate measurements of the incorporated radionuclides emitting X and gamma rays in the energy range of 10 keV–1500 keV, under conditions of good shielding, suitable collimation, and calibration. As an alternative to the experimental efficiency calibration method consisting of using reference calibration sources with gamma energy lines that cover all the considered energy range, it is proposed to use the Monte Carlo method for the efficiency calibration of the WBC using the radiation transport code MCNP5. The HPGe detector was modelled and the gamma energy lines of [Formula: see text]Am, [Formula: see text]Co, [Formula: see text]Ba, [Formula: see text]Cs, [Formula: see text]Co, and [Formula: see text]Eu were simulated in order to obtain the virtual efficiency calibration curve of the WBC. The Monte Carlo method was validated by comparing the simulated results with the experimental measurements using point-like sources. For their optimum matching, the impact of the variation of the front dead layer thickness and of the detector photon absorbing layers materials on the HPGe detector efficiency was studied, and the detector’s model was refined. In order to perform the WBC efficiency calibration for realistic people monitoring, more numerical calculations were generated simulating extended sources of specific shape according to the standard man characteristics.

X-Ray Microanalysis Combined with Monte Carlo Simulation for the Analysis of Layered Thin Films: The Case of Carbon Contamination

2009 ◽  
Vol 15 (2) ◽  
pp. 99-105 ◽  
Author(s):  
Aldo Armigliato ◽  
Rodolfo Rosa
Keyword(s):  
Monte Carlo ◽  
Carbon Film ◽  
Sample Surface ◽  
Scanning Transmission Electron Microscope ◽  
Carbon Layer ◽  
Monte Carlo Code ◽  
X Ray ◽  
Transmission Electron ◽  
The Monte Carlo Method ◽  
Scanning Transmission

AbstractA previously developed Monte Carlo code has been extended to the X-ray microanalysis in a (scanning) transmission electron microscope of plan sections, consisting of bilayers and triple layers. To test the validity of this method for quantification purposes, a commercially available NiOx (x ∼ 1) thin film, deposited on a carbon layer, has been chosen. The composition and thickness of the NiO film and the thickness of the C support layer are obtained by fitting to the three X-ray intensity ratios I(NiK)/I(OK), I(NiK)/I(CK), and I(OK)/I(CK). Moreover, it has been investigated to what extent the resulting film composition is affected by the presence of a contaminating carbon film at the sample surface. To this end, the sample has been analyzed both in the (recommended) “grid downward” geometry and in the upside/down (“grid upward”) situation. It is found that a carbon contaminating film of few tens of nanometers must be assumed in both cases, in addition to the C support film. Consequently, assuming the proper C/NiOx/C stack in the simulations, the Monte Carlo method yields the correct oxygen concentration and thickness of the NiOx film.

Free-Form Reflector Design Using Differential Evolution Algorithm

2007 ◽  
Vol 364-366 ◽  
pp. 138-142
Author(s):  
Bo Yang ◽  
Guo Fan Jin ◽  
Yong Tian Wang
Keyword(s):  
Monte Carlo ◽  
Differential Evolution ◽  
Ray Tracing ◽  
Differential Evolution Algorithm ◽  
Merit Function ◽  
Free Form ◽  
Design Technique ◽  
Merit Functions ◽  
Nurbs Surface ◽  
Evolution Algorithm

NURBS surface representation, combined with Differential Evolution (DE), enables us to perform automated non-imaging reflector design. The overall result is a simple automated nonimaging reflector design technique and only a little data such as desired illuminance distribution and searching limits are needed. Merit functions specific to non-imaging reflector design are presented. Using different merit functions, the generated illuminance distribution can be uniform as well as concentrated. DE is performed to obtain the reflector that generates the desired illuminance distribution. The photometric distributions are calculated through Monte-Carlo ray tracing and the illuminance value is used to calculate the merit function value. The validity of the proposed approach is demonstrated by optimization examples. Almost the same uniform illuminance distribution can be obtained using the algorithm proposed in this paper as that obtained by edge-raymethod. A concentrated illuminance distribution can also be generated using the algorithm proposed.

GERMANIUM DETECTOR EFFICIENCY FOR A MARINELLI BEAKER SOURCE-GEOMETRY USING THE MONTE CARLO METHOD

2002 ◽  
Vol 20 (2) ◽  
pp. 161-170 ◽  
Author(s):  
Ita O. B. Ewa ◽  
Denes Bodizes ◽  
Szaboles Czifrus ◽  
Marta Balla ◽  
Zsuzsa Molnar
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Method ◽  
Germanium Detector ◽  
Detector Efficiency ◽  
Marinelli Beaker ◽  
The Monte Carlo Method ◽  
Source Geometry

scholarly journals MAPPING OF SODIUM VOID EFFECT AND DOPPLER CONSTANT IN ESFR-SMART CORE WITH MONTE CARLO CODE SERPENT AND DETERMINISTIC CODE ERANOS

2021 ◽  
Vol 247 ◽  
pp. 13004
Author(s):  
Jiri Krepel ◽  
Valeria Raffuzzi
Keyword(s):  
Monte Carlo ◽  
Inner Core ◽  
Fuel Cycle ◽  
Cycle Performance ◽  
Monte Carlo Code ◽  
Stochastic Noise ◽  
Sodium Fast Reactor ◽  
The Monte Carlo Method ◽  
Void Effect ◽  
Gen Iv

The Sodium Fast Reactor is one of the most technologically developed Gen-IV reactors, which can close the nuclear fuel cycle. Its criticality safety directly depends on the sodium void effect and Doppler constant. Hence the knowledge of their local distribution is important. These coefficients can be mapped by deterministic or Monte Carlo codes, where the latter provide higher modeling accuracy, but are also strongly computer demanding and subject to stochastic noise issues. In this study, the void effect and Doppler constant have been enumerated for the ESFR core by Serpent2 and ERANOS2 codes, preserving a six-batch operation scheme. The Serpent code was coupled to the Python script BBP to simulate batch-wise operation in a radially infinite inner core configuration; the ERANOS code was applied to the whole core geometry and the batch-wise operation was simulated by the EQL3D routine. Sodium void effect and Doppler constant spatial maps with different levels of refinement were produced, as well as the time evolution of the integral coefficients during the transition from initial cycle to equilibrium cycle. Both codes indicate deterioration of these coefficients during the transition. The equilibrium cycle performance of the inner core zone from the ERANOS calculation was compared with Serpent results and they showed reasonable agreement. For very fine mapping, the Monte Carlo method employed was computationally very demanding and the enumerated effect was lower than the stochastic noise. In general, the Serpent model practically excludes modeling assumptions and produces reliable results for reasonably sized maps, which can be combined if needed with the high spatial resolution results obtained by ERANOS simulations.

Using the Few-Group Approximation for Calculating Some Neutron-Physical Characteristics of VVER-1000 Core by Means of the MCU Monte-Carlo Code

2021 ◽  
Author(s):  
Artem S. Bikeev ◽  
Yulia S. Daichenkova ◽  
Mikhail A. Kalugin ◽  
Denis Shkarovsky ◽  
Vladislav V. Shkityr
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Method ◽  
Cross Sections ◽  
Optimal Number ◽  
Physical Characteristics ◽  
Monte Carlo Code ◽  
Special Version ◽  
The Monte Carlo Method ◽  
Scattering Anisotropy ◽  
Neutron Cross Sections

Abstract The main purpose of this work is to study the possibility of using the few-group approximation for calculation of some neutron-physical characteristics of VVER-1000 core by means of special version of MCU code. The Monte-Carlo method for VVER-1000 core neutron-physical characteristics calculation using the few-group approximation with an estimate of neutron cross sections “by location“ was provided and tested in this research. The reduction of calculation time due to the transition from a pointwise model of representation of cross sections to the few-group approximation and methodical error of this approach were evaluated. Optimal number of energy groups was determined. It was found that consideration of the scattering anisotropy leads to a significant decrease in methodical error. Ways of further reduction of methodical error were worked out.

A Modified Method for Correcting Instrumental Spectrum of High Hurity Germanium Detector

ANRI ◽  
2020 ◽  
Vol 0 (4) ◽  
pp. 14-28
Author(s):  
Aliaksei Zaharadniuk ◽  
Roman Lukashevich ◽  
Konstantin Syankovsky ◽  
Aleksandr Novichenko
Keyword(s):  
Hpge Detector ◽  
Germanium Detector ◽  
Smooth Curve ◽  
Detector Response ◽  
Response Matrix ◽  
Modified Method ◽  
High Purity Germanium ◽  
The Monte Carlo Method ◽  
True Shape ◽  
Corrected Spectrum

The paper considers an improved method for correcting the instrumental spectrum of a high purity germanium detector (HPGe detector) in the energy range (10–300 keV). The method uses a detector response matrix obtained by the Monte Carlo method, which allows to bring the appearance of the instrumental spectrum of the HPGe detector closer to its true shape by minimizing the influence of the detector response function. The main difference of this method from analogs is the additional deconvolution algorithm of the corrected spectrum, which makes it possible to obtain a smooth curve at the output.

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