Results 41 to 50 of about 16,330 (259)
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
doaj +1 more source
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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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
doaj +1 more source
Serpent and MCNP Calculations of the Energy Deposition in the Transformational Challenge Reactor
Nuclear science and engineering, 2021 This study focuses on the calculation of the energy deposition in the Transformational Challenge Reactor by two major Monte Carlo codes: Serpent and MCNP.
A. Talamo +7 more
semanticscholar +1 more source
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
doaj +1 more source
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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Nuclear Engineering and Technology, 2019 The mass attenuation coefficient μ m for eight rock samples having different chemical composition was simulated using the MCNP 5 code in energy range ( 0.002 MeV ≤ E ≤ 10 MeV ) .
K. Mahmoud, M. Sayyed, O. Tashlykov
semanticscholar +1 more source
Comparative Study on Fuel Assembly of Modular Gas-cooled Fast Reactor using MCNP and OpenMC Code
, 2021 The design study of GFR concepts comprises neutronic analysis of fuel pin and fuel assembly. The Monte Carlo method has advantages in three-dimensional (3D) geometry modeling but requires a high computation time.
H. Raflis +4 more
semanticscholar +1 more source