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Artículos de revistas sobre el tema "MCNP / Geant4"

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

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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.
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2

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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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 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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5

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 (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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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 (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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8

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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9

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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11

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 (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
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12

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 (2020): 1629–36. http://dx.doi.org/10.1109/tns.2020.2979657.

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13

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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14

Yang, Zi-Yi, Pi-En Tsai, Shao-Chun Lee, et al. "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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15

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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16

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 (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 T
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17

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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18

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 (2006): 337–41. http://dx.doi.org/10.1118/1.2150787.

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19

Nourreddine, Abdel-Mjid, Jonathan Collin, Nicolas Arbor, et al. "Assessment of photon and proton-induced activation in particles accelerators." Radiation Protection Dosimetry 200, no. 16-18 (2024): 1507–13. http://dx.doi.org/10.1093/rpd/ncae146.

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Abstract Nuclear activation affects all operating, future, or dismantled particle accelerators used in various fields, from medical applications to industrial applications. This work is concerned with the study of the radioactivity induced in various materials (Sc, Cu, Tb, Ta, W, Au) irradiated by hard Bremsstrahlung photons from an electron beam and by secondary neutrons induced by a proton beam. In both cases, the primary beam features an 18 MeV kinetic energy. We have performed Monte Carlo simulations with MCNP, GEANT4, FLUKA, and PHITS, coupled with the analytical codes CINDER’90 or FISPAC
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20

Yu, Qian, Liang Chen, Yanbin Zhang, et al. "Application of optical fiber-based neutron detectors in neutron measurement of a liquid lead-bismuth spallation target." Journal of Instrumentation 20, no. 06 (2025): P06045. https://doi.org/10.1088/1748-0221/20/06/p06045.

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Abstract A novel scintillator fiber detector system has been developed to assess, in real time, the relative neutron flux density across various spatial and energy domains within the liquid lead-bismuth target prototype. This system comprises of a four-channel detectors system based on 6LiF/ZnS, a pre-amplifier module, an FPGA-based acquisition card, and accompanying software. It was developed to measure thermal neutron flux density distributions and to monitor proton beam power during the operation of the target. The measures data correlated with results from Monte Carlo simulations using Gea
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21

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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22

Min, Sujung, Youngsu Kim, Kwang-Hoon Ko, et al. "Optimization of Plastic Scintillator for Detection of Gamma-Rays: Simulation and Experimental Study." Chemosensors 9, no. 9 (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. T
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23

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 (2011): 811–27. http://dx.doi.org/10.1088/0031-9155/56/3/017.

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24

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 (2021): 564–78. http://dx.doi.org/10.1088/1361-6498/ac057e.

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25

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 (2008): 2804. http://dx.doi.org/10.1118/1.2962095.

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26

Collin, Jonathan, Jean-Michel Horodynski, Nicolas Arbor, et al. "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. I
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27

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 (2018): 155010. http://dx.doi.org/10.1088/1361-6560/aad0bd.

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28

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 (2020): 1002–7. http://dx.doi.org/10.1016/j.net.2019.10.016.

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29

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 us
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30

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 (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 dist
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31

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 (2006): 454–59. http://dx.doi.org/10.1016/j.nima.2005.12.238.

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32

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 (2007): 219–30. http://dx.doi.org/10.1016/j.nimb.2006.11.061.

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33

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 (2014): 70–80. http://dx.doi.org/10.26583/npe.2014.2.08.

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34

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

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35

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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36

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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37

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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38

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

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39

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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40

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 (2011): T09001. http://dx.doi.org/10.1088/1748-0221/6/09/t09001.

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41

Tran, H. N., A. Marchix, A. Letourneau, et al. "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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42

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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43

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

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44

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 (2012): 6381–93. http://dx.doi.org/10.1088/0031-9155/57/20/6381.

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45

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 (2015): 4951–62. http://dx.doi.org/10.1088/0031-9155/60/13/4951.

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46

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 (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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47

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 (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
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48

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 (2014): 549–51. http://dx.doi.org/10.1134/s1547477114040232.

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49

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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50

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 (2015): 14–19. http://dx.doi.org/10.1016/j.nucet.2015.11.004.

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