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Journal articles on the topic 'MCNP / Geant4'

Author: Grafiati
Published: 12 October 2024

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1

Wilson, Emma, Mike Anderson, David Prendergasty, and David Cheneler. "Comparison of CdZnTe neutron detector models using MCNP6 and Geant4." EPJ Web of Conferences 170 (2018): 08008. http://dx.doi.org/10.1051/epjconf/201817008008.

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The production of accurate detector models is of high importance in the development and use of detectors. Initially, MCNP and Geant were developed to specialise in neutral particle models and accelerator models, respectively; there is now a greater overlap of the capabilities of both, and it is therefore useful to produce comparative models to evaluate detector characteristics. In a collaboration between Lancaster University, UK, and Innovative Physics Ltd., UK, models have been developed in both MCNP6 and Geant4 of Cadmium Zinc Telluride (CdZnTe) detectors developed by Innovative Physics Ltd. Herein, a comparison is made of the relative strengths of MCNP6 and Geant4 for modelling neutron flux and secondary γ-ray emission. Given the increasing overlap of the modelling capabilities of MCNP6 and Geant4, it is worthwhile to comment on differences in results for simulations which have similarities in terms of geometries and source configurations.
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2

Varignier, Geoffrey, Valentin Fondement, Cédric Carasco, Johann Collot, Bertrand Pérot, Thomas Marchais, Pierre Chuilon, Emmanuel Caroli, and Mai-Linh Doan. "Comparison between GEANT4 and MCNP for well logging applications." EPJ Web of Conferences 288 (2023): 01002. http://dx.doi.org/10.1051/epjconf/202328801002.

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MCNP and GEANT4 are two reference Monte Carlo nuclear simulators, MCNP being the standard in the Oil & Gas nuclear logging industry. While performing a simulation benchmark of these two software for the purpose of “Cased Hole” wellbore evaluation, discrepancies between MCNP and GEANT4 were observed: computational experiments were performed first in a theoretical and simplified environment using spherical models, then in a more realistic “Open Hole” wellbore context with simplified logging tools. Results of this comparison show an excellent overall agreement for gamma-gamma physics and an acceptable agreement for neutron-neutron physics. However, the agreement for neutron-gamma physics is satisfactory only for certain lithologies and energy windows, but not acceptable for other operating conditions. These results need to be put in perspective with the current use of nuclear simulation in the logging industry. Indeed, wellbore evaluations rely on charts simulated with Monte Carlo codes in various contexts. In the case of radially heterogeneous environments such as “Cased Hole” wellbores, nuclear simulations are mandatory to precisely determine the radial sensitivity of logging tools via the so-called sensitivity functions. The feasibility of wellbore inversion relies on the physical validity of such sensitivity functions obtained from nuclear simulations. This MCNP vs. GEANT4 benchmark was conducted with the perspective to secure the physical fundamentals used for building the sensitivity functions of logging tools.
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3

Hrytsiuk, C. V., А. M. Bozhuk, А. V. Nosovskyi, and V. І. Gulik. "Cross-Verification of Monte Carlo Codes Geant4 and MCNP6 for Muon Tomography." Nuclear Power and the Environment 21, no. 2 (2021): 49–60. http://dx.doi.org/10.31717/2311-8253.21.2.5.

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Muon tomography is a promising detection technology that uses natural radiation, the muons of cosmic rays. In the last decade, a significant number of scientific papers have appeared that investigate the possibility of using muon tomography in various fields of science and technology. Especially remarkable is the considerable potential of this technology for detecting the illegal transport of radioactive materials and for no-invasive testing of the integrity of spent nuclear fuel in dry storage facilities for such fuel. For the implementation of muon tomography technology, the process of preliminary modeling of the experimental detector facility is important, which also requires verification of the obtained calculation results. For this purpose, the well-known Monte Carlo codes MCNP and Geant4 are mainly used. This results of the first cross-verification studies of MCNP6 and Geant4 codes are demonstrated in the paper. The study was performed on simple models for different materials and for different energies of the muons bombarding the research object. The recommended QGSP_BERT physics library was used in the Geant4 code. In the MCNP6 code, the recommended settings for cosmic particle simulations were used. The calculations showed that for low-energy muons, both codes give results that agree well with each other. This can be explained by the fact that similar libraries of evaluated nuclear data are used in the low-energy range. Regarding the muons of intermediate energies, there is a significant difference between the two codes, which may indicate differences in physical models. The modeling of high-energy muon transfer has better agreement between MCNP6 and Geant4 codes than for intermediate-energy muons, but significant differences are still observed for heavy nuclei.
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Matuszak, Natalia. "Monte Carlo jako jedna z metod symulacyjnych w radioterapii." Letters in Oncology Science 16, no. 2 (June 10, 2019): 15–22. http://dx.doi.org/10.21641/los.2019.17.2.91.

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Obecnie fizyka jądrowa coraz częściej stwarza możliwości ku nowym rozwiązaniom w radioterapii. Celem udoskonalenia już istniejących metod jest poszukiwanie bardziej precyzyjnych technologii dających możliwie jak najmniejsze ryzyko błędu. Fizyczne planowanie eksperymentów nierzadko wiąże się z ograniczeniami technicznymi, dlatego dobrym rozwiązaniem staje się modelowanie komputerowe. Do celów radioterapii najczęściej wymienianą metodą jest tzw. metoda Monte Carlo.Istotą tej metody jest symulacja komputerowa procesów o charakterze losowym. W oparciu o nią, algorytm wykorzystuje obliczenia numeryczne do opisu wielkości fizycznych. Stanowi to alternatywę dla procesów zbyt złożonych, dla których podejście analityczne jest niewystarczające by osiągnąć zamierzone cele. Spośród różnych kodów bazujących na obliczeniach Monte Carlo (MCNP, MCNPX, FLUKA, EGSnrc), w radioterapii największe zastosowanie znajduje GEANT4.
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Novikov, N. V. "Monte Carlo Computer Simulation Method for Solving the Problem of Particle Passage through Matter." Поверхность. Рентгеновские, синхротронные и нейтронные исследования, no. 6 (June 1, 2023): 94–106. http://dx.doi.org/10.31857/s1028096023060122.

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The Monte Carlo method is compared with the deterministic methods based on the solution of the transport equation and the molecular dynamics methods. The capabilities of commonly used general-purpose programs (SRIM, PENELOPE, MCNP, FLUKA, and GEANT4) for Monte Carlo simulation of the processes of particle passage through matter are analyzed. Possible ways for further development of the Monte Carlo method are discussed.
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6

Barton, C. J., W. Xu, R. Massarczyk, and S. R. Elliott. "Examining LEGEND-1000 cosmogenic neutron backgrounds in Geant4 and MCNP." Journal of Instrumentation 19, no. 05 (May 1, 2024): P05056. http://dx.doi.org/10.1088/1748-0221/19/05/p05056.

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Abstract For next-generation neutrinoless double beta decay experiments, extremely low backgrounds are necessary. An understanding of in-situ cosmogenic backgrounds is critical to the design effort. In-situ cosmogenic backgrounds impose a depth requirement and especially impact the choice of host laboratory. Often, simulations are used to understand background effects, and these simulations can have large uncertainties. One way to characterize the systematic uncertainties is to compare unalike simulation programs. In this paper, a suite of neutron simulations with identical geometries and starting parameters have been performed with Geant4 and MCNP, using geometries relevant to the LEGEND-1000 experiment. This study is an important step in gauging the uncertainties of simulations-based estimates. To reduce project risks associated with simulation uncertainties, a novel alternative shield of methane-doped liquid argon is considered in this paper for LEGEND-1000, which could achieve large background reduction without requiring significant modification to the baseline design.
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7

DiJulio, Douglas D., Isak Svensson, Xiao Xiao Cai, Joakim Cederkall, and Phillip M. Bentley. "Simulating neutron transport in long beamlines at a spallation neutron source using Geant4." Journal of Neutron Research 22, no. 2-3 (October 20, 2020): 183–89. http://dx.doi.org/10.3233/jnr-190134.

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The transport of neutrons in long beamlines at spallation neutron sources presents a unique challenge for Monte-Carlo transport calculations. This is due to the need to accurately model the deep-penetration of high-energy neutrons through meters of thick dense shields close to the source and at the same time to model the transport of low- energy neutrons across distances up to around 150 m in length. Typically, such types of calculations may be carried out with MCNP-based codes or alternatively PHITS. However, in recent years there has been an increased interest in the suitability of Geant4 for such types of calculations. Therefore, we have implemented supermirror physics, a neutron chopper module and the duct-source variance reduction technique for low- energy neutron transport from the PHITS Monte-Carlo code into Geant4. In the current work, we present a series of benchmarks of these extensions with the PHITS software, which demonstrates the suitability of Geant4 for simulating long neutron beamlines at a spallation neutron source, such as the European Spallation Source, currently under construction in Lund, Sweden.
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Karailias, A., V. Lagaki, C. Katsiva, A. Kanellakopoulos, T. J. Mertzimekis, F. C. Kafantaris, and A. Godelitsas. "The Athens Mobile γ-Spectrometry System (AMESOS)." HNPS Proceedings 23 (March 8, 2019): 150. http://dx.doi.org/10.12681/hnps.1894.

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We report on a new mobile γ-spectrometry system (AMESOS) developed at the University of Athens. The system aims at carrying out in situ measurements to study distributions of NORM and TENORM at harsh environments or where sampling is difficult. AMESOS has been characterized by using standard calibration sources and minerals of known, independently determined, U and Th concentrations. Simulations of the system have been performed with MCNP and Geant4. As a proof of good field operation, AMESOS was deployed in a series of measurements at Mt. Kithaeron, near Athens, extending earlier data and estimating absorbed dose rates that concern the public.
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9

Tsormpatzoglou, Ioannis, Anastasia Ziagkova, Michael Kokkoris, Maria Diakaki, Roza Vlastou, and Kalliopi Kaperoni. "Cross Section Biasing Technique in 3H(d,n)4He Reaction using the GEANT4 Toolkit." HNPS Advances in Nuclear Physics 30 (July 31, 2024): 250–55. http://dx.doi.org/10.12681/hnpsanp.6289.

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Simulations using Monte Carlo GEANT4 [1] toolkit was performed to quantify parasitic neutrons production from the 3H(d,n)4He reaction in the TANDEM [2] accelerator laboratory at N.C.S.R "Demokritos". In this reaction, parasitic neutrons are produced, which contaminate the main neutron beam. For studying parasitic neutrons, the cross section biasing technique has been applied to increase the cross sections of the reactions and to obtain accurate statistical results in a short computational time. However, the implementation of a biasing technique can significantly impact the physical processes simulated. The experimental setup contains the accelerator line and the tritium flange, which consists of molybdenum, tritium and copper. Then, the target materials are purposefully exposed to the neutron beam to conduct cross section measurement experiments. The simulation code aims to understand neutron flux distribution and transport through the targets. Finally, the corresponding results obtained using GEANT4, through the application of biasing techniques, were compared to those resulting from the combined use of the MCNP 6.1 [3] and NeuSDesc [4] codes.
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10

Fardi, Zeinab, and Payvand Taherparvar. "A Monte Carlo investigation of the dose distribution for new I-125 Low Dose Rate brachytherapy source in water and in different media." Polish Journal of Medical Physics and Engineering 25, no. 1 (March 1, 2019): 15–22. http://dx.doi.org/10.2478/pjmpe-2019-0003.

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Abstract Permanent and temporary implantation of I-125 brachytherapy sources has become an official method for the treatment of different cancers. In this technique, it is essential to determine dose distribution around the brachytherapy source to choose the optimal treatment plan. In this study, the dosimetric parameters for a new interstitial brachytherapy source I-125 (IrSeed-125) were calculated with GATE/GEANT4 Monte Carlo code. Dose rate constant, radial dose function and 2D anisotropy function were calculated inside a water phantom (based on the recommendations of TG-43U1 protocol), and inside several tissue phantoms around the IrSeed-125 capsule. Acquired results were compared with MCNP simulation and experimental data. The dose rate constant of IrSeed-125 in the water phantom was about 1.038 cGy·h−1U−1 that shows good consistency with the experimental data. The radial dose function at 0.5, 0.9, 1.8, 3 and 7 cm radial distances were obtained as 1.095, 1.019, 0.826, 0.605, and 0.188, respectively. The results of the IrSeed-125 is not only in good agreement with those calculated by other simulation with MCNP code but also are closer to the experimental results. Discrepancies in the estimation of dose around IrSeed-125 capsule in the muscle and fat tissue phantoms are greater than the breast and lung phantoms in comparison with the water phantom. Results show that GATE/GEANT4 Monte Carlo code produces accurate results for dosimetric parameters of the IrSeed-125 LDR brachytherapy source with choosing the appropriate physics list. There are some differences in the dose calculation in the tissue phantoms in comparison with water phantom, especially in long distances from the source center, which may cause errors in the estimation of dose around brachytherapy sources that are not taken account by the TG43-U1 formalism.
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11

Jun, Bongim, Brian Xiaoyu Zhu, Luz Maria Martinez-Sierra, and Insoo Jun. "Intercomparison of Ionizing Doses From Space Shielding Analyses Using MCNP, Geant4, FASTRAD, and NOVICE." IEEE Transactions on Nuclear Science 67, no. 7 (July 2020): 1629–36. http://dx.doi.org/10.1109/tns.2020.2979657.

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12

Sharabiani, M., M. Vaez-zadeh, and S. Asadi. "Size dependence of GNPs dose enhancement effects in cancer treatment – Geant4 and MCNP code." Radiotherapy and Oncology 118 (February 2016): S96—S97. http://dx.doi.org/10.1016/s0167-8140(16)30198-0.

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13

Yang, Zi-Yi, Pi-En Tsai, Shao-Chun Lee, Yen-Chiang Liu, Chin-Cheng Chen, Tatsuhiko Sato, and Rong-Jiun Sheu. "Inter-comparison of Dose Distributions Calculated by FLUKA, GEANT4, MCNP, and PHITS for Proton Therapy." EPJ Web of Conferences 153 (2017): 04011. http://dx.doi.org/10.1051/epjconf/201715304011.

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14

Singh, Vishwanath P., M. E. Medhat, and S. P. Shirmardi. "Comparative studies on shielding properties of some steel alloys using Geant4, MCNP, WinXCOM and experimental results." Radiation Physics and Chemistry 106 (January 2015): 255–60. http://dx.doi.org/10.1016/j.radphyschem.2014.07.002.

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15

Park, Junsung, Geunyoung An, Seonkwang Yoon, and Hee Seo. "Experimental validation of Monte Carlo simulation model for X-ray security scanner." Journal of Instrumentation 19, no. 01 (January 1, 2024): C01050. http://dx.doi.org/10.1088/1748-0221/19/01/c01050.

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Abstract Transmission X-ray security scanners are deployed to detect smuggling of contraband articles, including weapons, narcotics, and explosives, for the purposes of homeland security. Current X-ray scanners use a fixed tube voltage (i.e., 160 kV); hence, they have a limitation in detecting thinly coated and/or low-density objects. To overcome this limitation, we are developing an X-ray scanner that applies variable tube voltage according to the physical/chemical properties of the object being inspected. To this end, in our previous study, Monte Carlo simulations with Geant4 (GEometry ANd Tracking4) and MCNP (Monte Carlo N Particle) were performed to optimize the design of the X-ray scanner for variable tube voltages. The MCNP was used to simulate the radiation generator for the X-ray source term, and the Geant4 was used to optimize the design of the dual-energy detector and to obtain the detector counts. In the present study, we experimentally validated the reliability of the Monte Carlo simulation model for the X-ray scanner. An 241Am source and a radiation generator were employed in this validation. For the 241Am source, the dual-energy detector signal was measured at a distance of 1 cm from the detector. In the case of the radiation generator, the source-to-object distance and the source-to-detector distance were 70 cm and 120 cm, respectively, as used in a typical X-ray security scanner. The tube voltage and the current were 140 kV and 10 mA, respectively. To obtain the X-ray images, the object was scanned while moving at a speed of 0.2 m/s on a conveyor system. The X-ray source term used in the simulation was obtained by monoenergetic-electron-beam bombardment onto the target. 4-D simulations were performed for the moving object. To validate the simulation model, we compared the simulated and measured image profiles, as well as the pixel counts of the dual-energy detector. The percent differences between the simulated and measured pixel counts and the image profiles were all within 5%. Thus, we concluded that our simulation model for the X-ray scanner can be considered to be reliable.
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Mohammed, K. Saeed, and Ali M. Asiri Abdullah. "EYE-LENS DOSE COEFFICIENTS: A SIMULATION STUDY COMPARING OPERATIONAL DOSE USING MCNP AND GEANT4 MONTE CARLO SIMULATION CODES." Russian Electronic Journal of Radiology 11, no. 4 (2021): 122–28. http://dx.doi.org/10.21569/2222-7415-2021-11-4-122-128.

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Enger, Shirin A., Per Munck af Rosenschöld, Arash Rezaei, and Hans Lundqvist. "Monte Carlo calculations of thermal neutron capture in gadolinium: A comparison of GEANT4 and MCNP with measurements." Medical Physics 33, no. 2 (January 13, 2006): 337–41. http://dx.doi.org/10.1118/1.2150787.

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18

Hartling, K., B. Ciungu, G. Li, G. Bentoumi, and B. Sur. "The effects of nuclear data library processing on Geant4 and MCNP simulations of the thermal neutron scattering law." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 891 (May 2018): 25–31. http://dx.doi.org/10.1016/j.nima.2018.02.053.

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19

Min, Sujung, Youngsu Kim, Kwang-Hoon Ko, Bumkyung Seo, JaeHak Cheong, Changhyun Roh, and Sangbum Hong. "Optimization of Plastic Scintillator for Detection of Gamma-Rays: Simulation and Experimental Study." Chemosensors 9, no. 9 (August 25, 2021): 239. http://dx.doi.org/10.3390/chemosensors9090239.

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Plastic scintillators are widely used in various radiation measurement applications, and the use of plastic scintillators for nuclear applications including decommissioning, such as gamma-ray detection and measurement, is an important concern. With regard to efficient and effective gamma-ray detection, the optimization for thickness of plastic scintillator is strongly needed. Here, we elucidate optimization of the thickness of high-performance plastic scintillator using high atomic number material. Moreover, the EJ-200 of commercial plastic scintillators with the same thickness was compared. Two computational simulation codes (MCNP, GEANT4) were used for thickness optimization and were compared with experimental results to verify data obtained by computational simulation. From the obtained results, it was confirmed that the difference in total counts was less than 10% in the thickness of the scintillator of 50 mm or more, which means optimized thickness for high efficiency gamma-ray detection such as radioactive 137Cs and 60CO. Finally, simulated results, along with experimental data, were discussed in this study. The results of this study can be used as basic data for optimizing the thickness of plastic scintillators using high atomic number elements for radiation detection and monitoring.
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Maigne, L., Y. Perrot, D. R. Schaart, D. Donnarieix, and V. Breton. "Comparison of GATE/GEANT4 with EGSnrc and MCNP for electron dose calculations at energies between 15 keV and 20 MeV." Physics in Medicine and Biology 56, no. 3 (January 14, 2011): 811–27. http://dx.doi.org/10.1088/0031-9155/56/3/017.

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21

Frosio, Thomas, Philippe Bertreix, Nabil Menaa, and Samuel Thomas. "Calculation and benchmark of fluence-to-local skin equivalent dose coefficients for neutrons with FLUKA, MCNP, and GEANT4 Monte-Carlo codes." Journal of Radiological Protection 41, no. 3 (August 19, 2021): 564–78. http://dx.doi.org/10.1088/1361-6498/ac057e.

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22

Jiang, H. "SU-GG-T-343: Comparison of MCNP and GEANT4 Monte Carlo Codes On Photo-Neutron Generation in High Energy X-Ray Beams." Medical Physics 35, no. 6Part14 (June 2008): 2804. http://dx.doi.org/10.1118/1.2962095.

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Collin, Jonathan, Jean-Michel Horodynski, Nicolas Arbor, Massimo Barbagallo, Federico Carminati, Giuliana Galli Carminati, Luca J. Tagliapietra, and Abdel-Mjid Nourreddine. "Validation of Monte Carlo simulations by experimental measurements of neutron-induced activation in cyclotrons." EPJ Web of Conferences 288 (2023): 04025. http://dx.doi.org/10.1051/epjconf/202328804025.

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Nuclear activation is the process of production of radionuclides by irradiation. This phenomenon concerns particle accelerators used in various fields, from medical applications to industrial ones, both during operation and at the decommissioning phase. For more than three decades, the possibility of using cyclotrons for nuclear power generation and nuclear waste reduction has also been discussed, i.e. in the case of Accelerator-Driven Systems [1]. The radioprotection and dismantling issues of accelerator facilities, that have been raised recently, is even more potent for such installations. In our study, we are particularly interested in the activation due to secondary neutrons produced by (x,n) reactions, mostly (p,n) occurring in the accelerator’s components. This work focuses on the study of the radioactivity induced in various materials (V, Sc, Tb, W, Ta) irradiated by fast and thermal neutrons, in two different scenarios: through direct irradiation -with an AmBe sourceand around an operating cyclotron at the CYRCé facility (Strasbourg). A broad Monte Carlo study including FLUKA, GEANT4, PHITS and MCNP simulation has been performed, with and without a FISPACT-II coupling, to estimate the reaction rates and to trace the induced radioactivity in samples of known composition. The results of the simulations are compared with the values extracted in two dedicated experimental campaigns in which activated samples underwent high resolution gamma-ray spectrometry.
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Safigholi, Habib, and William Y. Song. "Calculation of water equivalent ratios for various materials at proton energies ranging 10–500 MeV using MCNP, FLUKA, and GEANT4 Monte Carlo codes." Physics in Medicine & Biology 63, no. 15 (July 27, 2018): 155010. http://dx.doi.org/10.1088/1361-6560/aad0bd.

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Nanbedeh, M., S. M. Sadat-Kiai, A. Aghamohamadi, and M. Hassanzadeh. "A feasibility study of the Iranian Sun mather type plasma focus source for neutron capture therapy using MCNP X2.6, Geant4 and FLUKA codes." Nuclear Engineering and Technology 52, no. 5 (May 2020): 1002–7. http://dx.doi.org/10.1016/j.net.2019.10.016.

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Zeman, Andrej, K. Tuček, G. Daquino, L. Debarberis, and A. Hogenbirk. "Scoring Analysis of Design, Verification and Optimization of High Intensity Positron Source (HIPOS)." Materials Science Forum 733 (November 2012): 297–305. http://dx.doi.org/10.4028/www.scientific.net/msf.733.297.

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As part of an exploratory research project at the Institute for Energy (Joint Research Centre of the European Commission), a feasibility assessment was performed for the design and construction of a high-intensity positron facility (HIPOS) in a neutron beam tube, HB9, at the High Flux Reactor (HFR) in Petten. The full model of reactor core, reflector and reactor instrumentation at the neutron beam line HB9 were modeled and full neutronic and photonic calculations were carried out by MCNP4C3. The source file was generated in two formats: SDEF and WESSA. Consequently, two different codes were used for scoring analysis for the optimization of the concept and geometry of positron generator. The main concept including key design parameters have been evaluated independently by two computer codes, in particular MCNP-X and GEANT4. The parametric design analysis including the optimization of positron generator at the pre-selected neutron beam line is reported in this paper. The detailed assessment of the critical design parameters, specifically from technological point of view is summarised. The results of independent analysis confirmed that the best approach is to combine two concepts of positron generation, which are based on the exploiting of neutron and gamma radiation. The results verified that the proposed concept can reach the defined threshold of the positron yield and the positron beam can reach an intensity of 1013e+/sec (un-moderated). The details of completed work are reported in this paper.
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Grządziel, Małgorzata, Adam Konefał, Wiktor Zipper, Robert Pietrzak, and Ewelina Bzymek. "Verification of the use of GEANT4 and MCNPX Monte Carlo Codes for Calculations of the Depth-Dose Distributions in Water for the Proton Therapy of Eye Tumours." Nukleonika 59, no. 2 (July 8, 2014): 61–66. http://dx.doi.org/10.2478/nuka-2014-0007.

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Abstract Verification of calculations of the depth-dose distributions in water, using GEANT4 (version of 4.9.3) and MCNPX (version of 2.7.0) Monte Carlo codes, was performed for the scatterer-phantom system used in the dosimetry measurements in the proton therapy of eye tumours. The simulated primary proton beam had the energy spectra distributed according to the Gauss distribution with the cut at energy greater than that related to the maximum of the spectrum. The energy spectra of the primary protons were chosen to get the possibly best agreement between the measured relative depth-dose distributions along the central-axis of the proton beam in a water phantom and that derived from the Monte Carlo calculations separately for the both tested codes. The local depth-dose differences between results from the calculations and the measurements were mostly less than 5% (the mean value of 2.1% and 3.6% for the MCNPX and GEANT4 calculations). In the case of the MCNPX calculations, the best fit to the experimental data was obtained for the spectrum with maximum at 60.8 MeV (more probable energy), FWHM of the spectrum of 0.4 MeV and the energy cut at 60.85 MeV whereas in the GEANT4 calculations more probable energy was 60.5 MeV, FWHM of 0.5 MeV, the energy cut at 60.7 MeV. Thus, one can say that the results obtained by means of the both considered Monte Carlo codes are similar but they are not the same. Therefore the agreement between the calculations and the measurements has to be verified before each application of the MCNPX and GEANT4 codes for the determination of the depth-dose curves for the therapeutic protons.
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Lemrani, R., M. Robinson, V. A. Kudryavtsev, M. De Jesus, G. Gerbier, and N. J. C. Spooner. "Low-energy neutron propagation in MCNPX and GEANT4." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 560, no. 2 (May 2006): 454–59. http://dx.doi.org/10.1016/j.nima.2005.12.238.

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Vilches, M., S. García-Pareja, R. Guerrero, M. Anguiano, and A. M. Lallena. "Monte Carlo simulation of the electron transport through thin slabs: A comparative study of penelope, geant3, geant4, egsnrc and mcnpx." Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 254, no. 2 (January 2007): 219–30. http://dx.doi.org/10.1016/j.nimb.2006.11.061.

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Solovyev, Alexey Nikolaevich, Vladimir Victorovich Fedorov, Valentin Igorevich Kharlov, and Uliyana Alekseevna Stepanova. "Comparative analysis of MCNPX and GEANT4 for fast neutron radiation treatment planning." Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika 2014, no. 2 (July 2014): 70–80. http://dx.doi.org/10.26583/npe.2014.2.08.

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TABBAKH, F. "MCNPX and GEANT4 simulation of γ-ray polymeric shields." Pramana 86, no. 4 (November 27, 2015): 939–44. http://dx.doi.org/10.1007/s12043-015-1095-4.

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32

Tesse, Robin, Frédéric Stichelbaut, Nicolas Pauly, Alain Dubus, and Jonathan Derrien. "GEANT4 benchmark with MCNPX and PHITS for activation of concrete." Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 416 (February 2018): 68–72. http://dx.doi.org/10.1016/j.nimb.2017.12.006.

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Lee, Hyeonmin, Si Hyeong Sung, Seung Hun Shin, and Hee Reyoung Kim. "Dead layer estimation of an HPGe detector using MCNP6 and Geant4." Applied Radiation and Isotopes 192 (February 2023): 110597. http://dx.doi.org/10.1016/j.apradiso.2022.110597.

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34

Affonso, Renato Raoni Werneck, Caroline Mattos Barbosa, Roos S. F. Dam, William L. Salgado, Ademir X. da Silva, and César M. Salgado. "Comparison between codes MCNPX and Gate/Geant4 in volume fraction studies." Applied Radiation and Isotopes 164 (October 2020): 109226. http://dx.doi.org/10.1016/j.apradiso.2020.109226.

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35

Colonna, N., and S. Altieri. "SIMULATIONS OF NEUTRON TRANSPORT AT LOW ENERGY: A COMPARISON BETWEEN GEANT AND MCNP." Health Physics 82, no. 6 (June 2002): 840–46. http://dx.doi.org/10.1097/00004032-200206000-00012.

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36

Zabihi, Mohammad, Fadavi Mazinani Mohammad, and Mahdipour Seyed Ali. "Monte Carlo investigation of prostate cancer ion – therapy by using SOBP technique in the GEANT4 toolkit and MCNPX code." JOURNAL OF ADVANCES IN PHYSICS 8, no. 2 (April 15, 2015): 2078–83. http://dx.doi.org/10.24297/jap.v8i2.1513.

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Regarding the useful results concerned with an external radio-therapy in treatment of tumors, we consider in this paper a standard model of the human prostate phantom based on MIRD phantom for the Monte Carlo simulation in GEANT4 toolkit and also on MCNPX code for a prostate cancer treatment. We calculate the lateral as well as the dose profiles in the tumor region for both proton and alpha beams in a similar range, and finally having implemented the SOBP technique, we compare the results of the two beams in the corresponding codes used in this analysis.
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Ge, Yi, Jingang Liang, Qiong Zhang, Wei Tang, and Agustin Munoz-Garcia. "A comparison study of GEANT4 and MCNP6 on neutron-induced gamma simulation." Applied Radiation and Isotopes 190 (December 2022): 110514. http://dx.doi.org/10.1016/j.apradiso.2022.110514.

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38

Guardiola, C., K. Amgarou, F. García, C. Fleta, D. Quirion, and M. Lozano. "Geant4 and MCNPX simulations of thermal neutron detection with planar silicon detectors." Journal of Instrumentation 6, no. 09 (September 5, 2011): T09001. http://dx.doi.org/10.1088/1748-0221/6/09/t09001.

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39

Tran, H. N., A. Marchix, A. Letourneau, J. Darpentigny, A. Menelle, F. Ott, J. Schwindling, and N. Chauvin. "Comparison of the thermal neutron scattering treatment in MCNP6 and GEANT4 codes." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 893 (June 2018): 84–94. http://dx.doi.org/10.1016/j.nima.2018.02.094.

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40

Hecht, A. A., R. E. Blakeley, W. J. Martin, and E. Leonard. "Comparison of Geant4 and MCNP6 for use in delayed fission radiation simulation." Annals of Nuclear Energy 69 (July 2014): 134–38. http://dx.doi.org/10.1016/j.anucene.2014.02.004.

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41

Tabbakh, Farshid. "Particles Transportation and Nuclear Heating in a Tokamak by MCNPX and GEANT4." Journal of Fusion Energy 35, no. 2 (December 19, 2015): 401–6. http://dx.doi.org/10.1007/s10894-015-0047-9.

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42

Titt, U., B. Bednarz, and H. Paganetti. "Comparison of MCNPX and Geant4 proton energy deposition predictions for clinical use." Physics in Medicine and Biology 57, no. 20 (September 21, 2012): 6381–93. http://dx.doi.org/10.1088/0031-9155/57/20/6381.

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43

Archambault, John Paul, and Ernesto Mainegra-Hing. "Comparison between EGSnrc, Geant4, MCNP5 and Penelope for mono-energetic electron beams." Physics in Medicine and Biology 60, no. 13 (June 10, 2015): 4951–62. http://dx.doi.org/10.1088/0031-9155/60/13/4951.

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44

Newpower, Mark, Jan Schuemann, Radhe Mohan, Harald Paganetti, and Uwe Titt. "Comparing 2 Monte Carlo Systems in Use for Proton Therapy Research." International Journal of Particle Therapy 6, no. 1 (May 3, 2019): 18–27. http://dx.doi.org/10.14338/ijpt-18-00043.1.

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Abstract Purpose: Several Monte Carlo transport codes are available for medical physics users. To ensure confidence in the accuracy of the codes, they must be continually cross-validated. This study provides comparisons between MC2 and Tool for Particle Simulation (TOPAS) simulations, that is, between medical physics applications for Monte Carlo N-Particle Transport Code (MCNPX) and Geant4. Materials and Methods: Monte Carlo simulations were repeated with 2 wrapper codes: TOPAS (based on Geant4) and MC2 (based on MCNPX). Simulations increased in geometrical complexity from a monoenergetic beam incident on a water phantom, to a monoenergetic beam incident on a water phantom with a bone or tissue slab at various depths, to a spread-out Bragg peak incident on a voxelized computed tomography (CT) geometry. The CT geometry cases consisted of head and neck tissue and lung tissue. The results of the simulations were compared with one another through dose or energy deposition profiles, r90 calculations, and γ-analyses. Results: Both codes gave very similar results with monoenergetic beams incident on a water phantom. Systematic differences were observed between MC2 and TOPAS simulations when using a lung or bone slab in a water phantom, particularly in the r90 values, where TOPAS consistently calculated r90 to be deeper by about 0.4%. When comparing the performance of the 2 codes in a CT geometry, the results were still very similar, exemplified by a 3-dimensional γ-analysis pass rate > 95% at the 2%–2-mm criterion for tissues from both head and neck and lung. Conclusion: Differences between TOPAS and MC2 were minor and were not considered clinically relevant.
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Krylov, A., M. Paraipan, N. Sobolevsky, G. Timoshenko, and V. Tret’yakov. "GEANT4, MCNPX, and SHIELD code comparison concerning relativistic heavy ion interaction with matter." Physics of Particles and Nuclei Letters 11, no. 4 (July 2014): 549–51. http://dx.doi.org/10.1134/s1547477114040232.

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46

Dim, O. U., S. K. Aghara, and M. Kütt. "Comparison of the single and double count using MCNP6 and ONMS Geant4 software." Progress in Nuclear Energy 121 (March 2020): 103240. http://dx.doi.org/10.1016/j.pnucene.2020.103240.

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47

Solovyev, A. N., V. V. Fedorov, V. I. Kharlov, and U. A. Stepanova. "Comparative analysis of MCNPX and GEANT4 codes for fast-neutron radiation treatment planning." Nuclear Energy and Technology 1, no. 1 (September 2015): 14–19. http://dx.doi.org/10.1016/j.nucet.2015.11.004.

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48

Androulakaki, E., C. Tsabaris, D. L. Patiris, G. Eleftheriou, M. Kokkoris, and R. Vlastou. "In situ gamma-ray measurements of marine sediment using Monte Carlo simulation." HNPS Proceedings 20 (December 1, 2012): 139. http://dx.doi.org/10.12681/hnps.2499.

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This work outlines the progress in developing a new method for in situ radioactivity measurements of marine sediments. The method combines the underwater gamma-ray spectrometer (a system named KATERINA based on a NaI(Tl) detector) with Monte-Carlo calculations using the MCNP5 code. This method aims at allowing for an accurate quantitative determination of activity concentrations in marine sediments (using the in situ system), which can be applied in different areas and for variable sediment structures.As a first step, the MCNP5 code has been successfully applied for the standard 4π geometry in the aquatic environment, reproducing results of the marine efficiency as previously deduced by the GEANT4 code. The experimental set up geometry was introduced in MCNP5 using detailed information for the geometry and the materials. Moreover, a first simulated estimation of the in situ efficiency for sediment measurements is presented for 40K (1460.8 keV). For this purpose a new model was constructed taking into account a typical experimental geometry set-up (with the detector being situated in close contact with the seabed). In order to validate the Monte-Carlo results, activity measurements were also performed in sediment samples collected from Basilica, Cyprus, where the in situ system was deployed. The samples were analysed using a HPGe detector for inter-calibration purposes and the obtained results are discussed.
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Mendoza, E., D. Cano-Ott, D. Jordan, J. L. Tain, and A. Algora. "NuDEX: A new nuclear γ-ray cascades generator." EPJ Web of Conferences 239 (2020): 17006. http://dx.doi.org/10.1051/epjconf/202023917006.

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Evaluated nuclear data libraries written in ENDF-6 format are used by Monte Carlo codes such as Geant4, MCNP6 or FLUKA for the transport of low energy neutrons (up to 20 MeV). The format in which the production of γ-rays after neutron induced reactions is provided do not allow, in general, to generate these γ-ray cascades in a correlated way. This prevents, among other things, energy conservation event by event, which is crucial in many applications. We have developed a code capable to generate correlated de-excitation γ-ray cascades using as much information as possible available in the RIPL-3 and ENSDF nuclear structure data libraries, among other useful information. The code follows the same philosophy of the DICEBOX or DEGEN codes. It generates the complete level scheme and branching ratios of the nucleus by using all the information experimentally known (known level scheme and known branching ratios) and completing the missing information with the most reliable statistical models. This code is able to generate automatically cascades for a large variety of nuclei (∼300) without requiring a specific input for each particular isotope. The code has been written in C++ language and can be integrated in the Geant4 simulation toolkit framework.
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van der Ende, B. M., J. Atanackovic, A. Erlandson, and G. Bentoumi. "Use of GEANT4 vs. MCNPX for the characterization of a boron-lined neutron detector." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 820 (June 2016): 40–47. http://dx.doi.org/10.1016/j.nima.2016.02.082.

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