Results 21 to 30 of about 2,294 (180)
Determination of neutron spectrum parameters at IREN facility using the MCNP simulation and experimental validation [PDF]
Nuclear Technology and Radiation ProtectionThe determination of the characteristics of neutron spectrum at different irradiation positions on the outer wall of moderator chamber of the intense resonance neutron source by simulation method using MCNP code was presented.
Nhat Le Tran Minh +14 more
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Neutron-physical parameters at the outlet of the WWR-K reactor beam tube
Eurasian Journal of Physics and Functional Materials, 2021 The paper is devoted to the neutron-physical parameters obtained via combined calculations and experimental measurements for the exit of the WWR-K reactor beam tube.
A. B. Bauyrzhan +6 more
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Elaborate SMART MCNP Modelling Using ANSYS and Its Applications
EPJ Web of Conferences, 2017 An MCNP 3-dimensional model can be widely used to evaluate various design parameters such as a core design or shielding design. Conventionally, a simplified 3-dimensional MCNP model is applied to calculate these parameters because of the cumbersomeness ...
Song Jaehoon +3 more
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Süleyman Demirel Üniversitesi Fen-Edebiyat Fakültesi Fen Dergisi, 2021 Spine fixation is required in cases such as congenital spinal curvatures, vertebral fractures, sagittal collapse over time, painful kyphosis, and bone load due to tumors.
Hasan Özdoğan +3 more
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Bremsstrahlung conversion efficiency and gamma - neutron generation from polypropylene, aluminum, iron, and lead bombarded by 10 MeV electrons [PDF]
Nuclear Technology and Radiation Protection, 2020 An electron beam from the UELR-10-15S2 accelerator (average energy of 9.92 ± 0.48 MeV) was applied to irradiate food and medical items at the Research and Development Center for Radiation Technology, Vietnam Atomic Energy Institute, Vietnam. The
Tuan Nguyen Anh, Tao Chau Van
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Analysis of DD, TT and DT Neutron Streaming Experiments with the ADVANTG Code [PDF]
EPJ Web of Conferences, 2020 The paper presents an analysis of DD, TT and DT neutron streaming benchmark experiments with the recently released hybrid transport code ADVANTG (AutomateD VAriaNce reducTion Generator).
Kos Bor +8 more
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Comparison between GEANT4 and MCNP for well logging applications [PDF]
EPJ Web of Conferences, 2023 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 ...
Varignier Geoffrey +8 more
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RADIATION DAMAGE AND DPA IN IRON USING MCNP5 [PDF]
European Journal of Materials Science and Engineering, 2020 A Monte Carlo simulation code is developed for the study of neutron induced radiation damage in the materials which results from nuclear collision as well as reactions that create energetic recoil atoms of the host material or reaction creates.
Hiwa Mohammad QADR
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Brazilian Journal of Radiation Sciences, 2021 MCNP is a code extensively used to simulate experiments involving transport of radiation using the Monte Carlo method. This code allows the study of different geometries, materials, and radiation types (e.g.
Caroline Mattos Barbosa +5 more
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Data-driven discovery of meteotsunami patterns from sparse observations
Environmental Data ScienceMeteotsunamis—tsunami-like sea level oscillations generated by atmospheric disturbances—pose underestimated risks to coastal regions worldwide. Despite growing evidence of their frequency and impact, limited offshore observations and forecasting ...
Ardiansyah Fauzi +4 more
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