Bibliografías temáticas / MCNP / Geant4

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Literatura académica sobre el tema "MCNP / Geant4"

Autor: Grafiati
Publicado: 12 de octubre de 2024
Última modificación: 31 de julio de 2025

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Artículos de revistas sobre el tema "MCNP / Geant4"

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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.
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Varignier, Geoffrey, Valentin Fondement, Cédric Carasco, et al. "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 a
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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 preli
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4

Matuszak, Natalia. "Monte Carlo jako jedna z metod symulacyjnych w radioterapii." Letters in Oncology Science 16, no. 2 (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 numery
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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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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 (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 star
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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 (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 fo
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Karailias, A., V. Lagaki, C. Katsiva та ін. "The Athens Mobile γ-Spectrometry System (AMESOS)". HNPS Proceedings 23 (8 березня 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 est
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Varignier, Geoffrey, Pierre Chuilon, Emmanuel Caroli, et al. "Laboratory Experimental Validation of Sensitivity Functions for a Neutron Porosity Logging Tool in Casedhole Environments." Petrophysics – The SPWLA Journal of Formation Evaluation and Reservoir Description 66, no. 2 (2025): 294–316. https://doi.org/10.30632/pjv66n2-2025a7.

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Mature producing fields face the challenge of safely abandoning numerous wells. Casedhole logs can play a key role in the integrity and confinement assessment. Therefore, the industrial problem today is no longer to characterize some petrophysical properties of the rock formation but also some components of the well. Due to the large number of variables, a multiphysics inversion simultaneously considering different nuclear logs is mandatory. During the past 20 years, The University of Texas introduced the concept of flux sensitivity functions to predict logs and allow the inversion of formatio
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10

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 s
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Tesis sobre el tema "MCNP / Geant4"

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Varignier, Geoffrey. "Construction de fonctions de sensibilité spatiales et prédictions rapides de diagraphies nucléaires en environnement de puits tubés." Electronic Thesis or Diss., Université Grenoble Alpes, 2024. http://www.theses.fr/2024GRALY026.

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Dans les puits pétroliers, de nombreux outils fonctionnant sur différents principes physiques sont couramment utilisés pour l’acquisition de données. Cette thèse se concentre sur les sondes de diagraphies nucléaires actives, faisant intervenir une source neutronique ou gamma. Elles sont utilisées dans l'industrie pétrolière pour caractériser la géologie des puits et ont été initialement développées pour réaliser des mesures quantitatives en conditions puits ouvert où la sonde est en contact direct avec la formation rocheuse. Une fois le puits pétrolier foré, un tube en acier est installé puis
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2

Cognet, Marie-Anne. "Etude préliminaire de la mesure du rapport alpha, rapport de la section efficace moyenne de capture sur celle de fission de l'233U, sur la plateforme PEREN - Développement et étude du dispositif expérimental -." Phd thesis, Grenoble INPG, 2007. http://tel.archives-ouvertes.fr/tel-00269052.

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Cette thèse consiste en une étude préparatoire de la mesure du rapport alpha de l'233U entre 1eV et 10keV, facteur nécessaire pour calculer le pouvoir de régénération de réacteurs basés sur le cycle 232Th/233U. Cette mesure peut être effectuée au LPSC, sur la plateforme PEREN qui est composée d'un spectromètre à temps de ralentissement au plomb couplé à un GEnérateur de NEutrons Pulsé Intense (GENEPI). Les taux de capture et de fission sont mesurés grâce à 8 scintillateurs YAP utilisés en coïncidence et entourant une chambre à fission. Des mesures préliminaires sur l'235U ont présenté un rappo
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Cognet, Marie-Anne. "Étude préliminaire de la mesure du rapport alpha, rapport de la section efficace moyenne de capture sur celle de fission de l'233U, sur la plateforme PEREN - Développement et étude du dispositif expérimental -." Phd thesis, Grenoble INPG, 2007. http://www.theses.fr/2007INPG0159.

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Cette thèse consiste en une étude préparatoire de la mesure du rapport alpha de l'233U entre 1eV et 10keV, facteur nécessaire pour calculer le pouvoir de régénération de réacteurs basés sur le cycle 232Th/233U. Cette mesure peut être effectuée au LPSC, sur la plateforme PEREN qui est composée d'un spectromètre à temps de ralentissement au plomb couplé à un GEnérateur de NEutrons Pulsé Intense (GENEPI). Les taux de capture et de fission sont mesurés grâce à 8 scintillateurs YAP utilisés en coïncidence et entourant une chambre à fission. Des mesures préliminaires sur l’235U ont présenté un rappo
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4

Ogheard, Florestan. "Développement d’un système de mesure directe du débit d’émission de sources neutroniques." Thesis, Paris 11, 2012. http://www.theses.fr/2012PA112176/document.

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La méthode de mesure de référence du débit d’émission de sources neutroniques se fonde sur la technique du bain de manganèse. Elle est destinée à étalonner des sources de neutrons utilisant des radionucléides (241AmBe, 239PuBe, 252Cf,…) en termes de débit d’émission neutronique sous 4π sr. Ce dispositif est complété par un banc de mesure de l’anisotropie d’émission utilisant un support rotatif et un compteur long de type BF3. La source à mesurer est immergée dans une solution de sulfate de manganèse et les neutrons émis sont capturés par les constituants du bain. Dans une configuration classiq
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Ogheard, Florestan. "Développement d'un système de mesure directe du débit d'émission de sources neutroniques." Phd thesis, Université Paris Sud - Paris XI, 2012. http://tel.archives-ouvertes.fr/tel-00740509.

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La méthode de mesure de référence du débit d'émission de sources neutroniques se fonde sur la technique du bain de manganèse. Elle est destinée à étalonner des sources de neutrons utilisant des radionucléides (241AmBe, 239PuBe, 252Cf,...) en termes de débit d'émission neutronique sous 4π sr. Ce dispositif est complété par un banc de mesure de l'anisotropie d'émission utilisant un support rotatif et un compteur long de type BF3. La source à mesurer est immergée dans une solution de sulfate de manganèse et les neutrons émis sont capturés par les constituants du bain. Dans une configuration class
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Vanstalle, Marie. "Dosimétrie électronique et métrologie neutrons par capteur CMOS a pixels actifs." Phd thesis, Université de Strasbourg, 2011. http://tel.archives-ouvertes.fr/tel-00630288.

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Ce travail vise à démontrer la faisabilité d'un dosimètre opérationnel neutrons basé sur la technologie CMOS. Le capteur utilisé (MIMOSA-5) doit pour cela être transparent aux γ et pouvoir détecter les neutrons sur une large gamme d'énergie en gardant évidemment une bonne efficacité de détection. La réponse du système de détection, constitué du capteur CMOS adjoint d'un matériau convertisseur (polyéthylène pour les neutrons rapides, 10B pour les neutrons thermiques), a été confrontée à des si-mulations Monte Carlo effectuées avec MCNPX et GEANT4. Un travail de validation de ces codes a préalab
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Ordóñez, Ródenas José. "Desarrollo de Modelos de Simulación por Monte Carlo como Apoyo a la Medida de Radiactividad Ambiental en Operación Rutinaria y de Emergencias." Doctoral thesis, Universitat Politècnica de València, 2020. http://hdl.handle.net/10251/152188.

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[ES] En el apoyo a la mejora de la calidad de medida en el Laboratorio de Radiactividad Ambiental (LRA) de la Universitat Politècnica de València (UPV), los códigos de Monte Carlo representan una potente herramienta para complementar las tareas relacionadas con la medida de la radiactividad ambiental, tales como la calibración en eficiencia de detectores de semiconductor, determinación de factores de corrección por coincidencia y caracterización de dosímetros de termoluminiscencia, entre otras. En la presente Tesis se desarrollan modelos de simulación en Monte Carlo a través de códigos y herr
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Capítulos de libros sobre el tema "MCNP / Geant4"

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Autran Daniela Munteanu, Jean-Luc. "Radiation Response of Group-IV and III-V Semiconductors Subjected to D–D and D–T Fusion Neutrons." In New Advances in Semiconductors [Working Title]. IntechOpen, 2022. http://dx.doi.org/10.5772/intechopen.103047.

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This work focuses on the radiation response of Group IV (Si, Ge, SiC, diamond) and III-V (GaAs, GaN, GaP, GaSb, InAs, InP, InSb, AlAs) semiconductors subjected to D–D (2.45 MeV) and D–T (14 MeV) neutrons. The response of each material has been systematically investigated through a direct calculation using nuclear cross-section libraries, MCNP6, and Geant4 numerical simulations. For the semiconductor materials considered, we have investigated in detail the reaction rates per type of reaction (elastic, inelastic, and nonelastic) and proposed an exhaustive classification and counting of all the n
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Autran Daniela Munteanu, Jean-Luc. "Radiation Response of Group-IV and III-V Semiconductors Subjected to D–D and D–T Fusion Neutrons." In New Advances in Semiconductors [Working Title]. IntechOpen, 2022. http://dx.doi.org/10.5772/intechopen.103047.

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This work focuses on the radiation response of Group IV (Si, Ge, SiC, diamond) and III-V (GaAs, GaN, GaP, GaSb, InAs, InP, InSb, AlAs) semiconductors subjected to D–D (2.45 MeV) and D–T (14 MeV) neutrons. The response of each material has been systematically investigated through a direct calculation using nuclear cross-section libraries, MCNP6, and Geant4 numerical simulations. For the semiconductor materials considered, we have investigated in detail the reaction rates per type of reaction (elastic, inelastic, and nonelastic) and proposed an exhaustive classification and counting of all the n
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Actas de conferencias sobre el tema "MCNP / Geant4"

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Yung-Shun Yeh, Chung-Hsiang Wang, Hong-Ming Liu, Tsung-Che Liu, and Guey-Lin Lin. "Simulating neutron propagations with FLUKA, GEANT4 and MCNP." In 2007 IEEE Nuclear Science Symposium Conference Record. IEEE, 2007. http://dx.doi.org/10.1109/nssmic.2007.4436548.

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Romero–Barrientos, Jaime, F. Molina, Pablo Aguilera, and H. F. Arellano. "Calculation of self–shielding factor for neutron activation experiments using GEANT4 and MCNP." In THERMOPHYSICS 2016: 21st International Meeting. Author(s), 2016. http://dx.doi.org/10.1063/1.4955388.

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Naeem, Syed F., Shaun D. Clarke, and Sara A. Pozzi. "Comparison of GEANT4 and MCNPX-PoliMi fission models." In 2012 IEEE Nuclear Science Symposium and Medical Imaging Conference (2012 NSS/MIC). IEEE, 2012. http://dx.doi.org/10.1109/nssmic.2012.6551258.

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Zhang, Guoqing, Xuexin Wang, Jiangang Zhang, Dajie Zhuang, Chaoduan Li, and Fan Gao. "Electron and Beta Dose Rates of UO2 Pellet and Fuel Rod." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-15219.

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The isotopes of uranium and their daughter nuclides inside the UO2 pellet emit mono-energetic electrons and beta rays, which generate rather high dose rate near the UO2 pellet and could cause exposure to workers. In this work calculations of electron dose rates have been carried out with Monte Carlo codes, MCNPX and Geant4, for a UO2 pellet and a fuel rod. Comparisons between calculations and measurements have been carried out to verify the calculation results. The results could be used to estimate the dose produced by electrons and beta rays, which could be used to make optimization for radia
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Juste, B., D. Morera, R. Miro, and G. Verdu. "Calculation of energetic dual-energy detector efficiency using MCNP and GEANT Monte Carlo codes." In 2011 2nd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA). IEEE, 2011. http://dx.doi.org/10.1109/animma.2011.6172946.

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Geoffrey, Varignier, Pïerre Chuilon, Emmanuel Caroli, et al. "Experimental Validation of a Sensitivity Function Based Sigma Simulator in a Cased-Hole Environment With Calibration Facility and Production Well Data." In 2024 SPWLA 65th Annual Symposium. Society of Petrophysicists and Well Log Analysts, 2024. https://doi.org/10.30632/spwla-2024-0118.

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Mature producing areas face the challenge of abandoning numerous wells safely. Cased-hole logs can play a key role in the integrity and confinement assessment. Therefore, the industrial problem today is no longer to characterize some petrophysical properties of the formation (e.g., porosity, density, lithology, oil or gas saturation, etc.) but also some components of the well (e.g., drilling fluids, casing, and cement). Due to the large number of variables, a multiphysics inversion considering simultaneously different nuclear log inputs is mandatory. During the past 20 years, Austin University
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Hoang, Duc-Tam, Thien-Thanh Tran, Bao-Tran Le, et al. "First Results of Saturation Curve Measurements of Heat-Resistant Steel Using GEANT4 and MCNP5 Codes." In Proceedings of the Conference on Advances in Radioactive Isotope Science (ARIS2014). Journal of the Physical Society of Japan, 2015. http://dx.doi.org/10.7566/jpscp.6.030144.

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Shtejer, K., J. D. T. Arruda-Neto, R. Schulte, et al. "Comparison of MCNPX and GEANT4 to Predict the Contribution of Non-elastic Nuclear Interactions to Absorbed Dose in Water, PMMA and A150." In MEDICAL PHYSICS: Tenth Mexican Symposium on Medical Physics. AIP, 2008. http://dx.doi.org/10.1063/1.2979250.

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Informes sobre el tema "MCNP / Geant4"

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Mendoza, E., and Daniel Cano-Ott. Update of the Evaluated Neutron Cross Section Libraries for the Geant4 Code. IAEA Nuclear Data Section, 2018. http://dx.doi.org/10.61092/iaea.5knd-4xdd.

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The list of evaluated neutron data libraries in Geant4 format distributed by the IAEA nuclear data service has been updated with six new releases: JEFF-3.3, JEFF-3.2, ENDF/B-VIII.0, ENDF/B-VII.1, BROND-3.1 and JENDL-4.0u (version 2016/1/6). In this report we provide some information concerning the transformation of these six new releases from the ENDF-6 data format into the Geant4 format. In addition, we present a comparison between results obtained with Geant4 and MCNP6 when using these libraries.
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Sweger, Zachary. Simulations of Neutron Time-of-Flight Method by Inelastic Scattering Carbon-12 using MCNP6 and Geant4. Office of Scientific and Technical Information (OSTI), 2019. http://dx.doi.org/10.2172/1532622.

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