Results 101 to 110 of about 1,341 (152)

Comparative analysis of Monte Carlo simulations and experimental evaluation of PMMA reinforced with hgo for gamma radiation shielding. [PDF]

Sci Rep
Mokhtari Dorostkar M, Abdi Saray A.
europepmc   +1 more source

Modelo y validación del reactor nuclear AKR2 y diseño de una fuente de neutrones fríos con los códigos de transporte de partículas Serpent2 y MCNP6

, 2017
Proyecto confidencial (Riunet)Beltrá Picó, A. (2017). Modelo y validación del reactor nuclear AKR2 y diseño de una fuente de neutrones fríos con los códigos de transporte de partículas Serpent2 y MCNP6.
Beltrá Picó, Adrián
core  

Assessment of Radiation Attenuation Properties in Dental Implants Using Monte Carlo Method. [PDF]

Bioengineering (Basel)
Rasat A, Tunc S, Uncu YA, Ozdogan H.
europepmc   +1 more source

Comparison of 3DCRT and IMRT out-of-field doses in pediatric patients using Monte Carlo simulations with treatment planning system calculations and measurements. [PDF]

Front Oncol, 2022
Sá AC, Barateiro A, Bednarz BP, Almeida P, Vaz P, Madaleno T.   +5 more
europepmc   +1 more source

Development of PMMA based polymer composite incorporating WO₃ for gamma radiation shielding using synthesis and Monte Carlo simulation. [PDF]

Sci Rep
Mokhtari Dorostkar M, Abdi Saray A.
europepmc   +1 more source

Assessment of ITER radiation environment during the remote-handling operation of In-Vessel components with D1SUNED. [PDF]

Sci Rep, 2023
Martínez-Albertos P, Sauvan P, Loughlin MJ, Le Tonqueze Y, Juárez R.   +4 more
europepmc   +1 more source

Use of Different Reactor Physics Models and CADIS Accelerated MCNP to Yield a 1 MeV Silicon Equivalent Flux for Neutron Damage. [PDF]

IEEE Trans Nucl Sci
Johnson JA, Sjoden GE, Kimball TS, Vince Wang MJ.   +3 more
europepmc   +1 more source

Design and implementation of the first proton beam transport line in VEGA-3 Petawatt laser system. [PDF]

Sci Rep
Cebriano Ramírez T, Curcio A, Apiñaniz Aginako JI, De Luis Blanco D, Morabito A, Salgado-López C, Filippov E, Rodríguez Frías MD, Volpe L, Gatti G.   +9 more
europepmc   +1 more source

VVER-1000 fuel assembly model in CAD-based unstructured mesh for MCNP6

, 2018
Geometry models for Monte Carlo transport codes have been using standard constructive solid geometry (CSG). The standard approach is using analytical equations for defining surfaces from which spatial cells are constructed.
Vimpel, Jan, Lovecký, Martin, Závorka, Jiří   +2 more
core  

Monte Carlo simulations of 241 Am α -particle energy distribution, LET distribution, and absorbed dose in a cell layer. [PDF]

Med Phys
Araszkiewicz M, Tymińska K, Kaźmierczak U, Chuchała P, Grzyb J, Kamińska P, Kwiatkowski R, Maleszewska M, Malinowska A, Maliszewska-Olejniczak K, Paterczyk B, Korgul A.   +11 more
europepmc   +1 more source