Results 181 to 190 of about 2,139 (206)

SIMULATION OF THE FEOKTISTOV TRAVELING WAVE OF NUCLEAR BURNING IN URANIUM WITH THE MCNPX CODE

Problems of Atomic Science and Technology
A mathematical simulation of the Feoktistov traveling wave of nuclear burning in depleted uranium was performed using the Monte Carlo method using the MCNPX code supplemented with reactivity feedback in order to find the value of the steady-state power of the system.
V.V. Gann, G.V. Gann
openaire   +1 more source

Studies on Production of Neutrons in the Spallation Reactions Using the Monte Carlo Code MCNPX

Nuclear Science and Engineering, 2012
AbstractThe accelerator-driven system (ADS) is an innovative reactor that is being considered as a dedicated high-level-waste burner in a double-strata fuel cycle. (“Double-strata fuel cycle” means a partitioning and transmutation system for long-lived radioactive nuclides.) The target is the physical and functional interface between the accelerator ...
Heba Louis, Esmaat Amin, Moustafa Aziz, Ibrahim Bashter   +3 more
openaire   +1 more source

Radioactive particle tracking methodology to evaluate concrete mixer using MCNPX code

Radiation Physics and Chemistry, 2019
Abstract In Brazil, concrete and cement are highly used in construction, therefore mixers are widely used in this industry. During the fabrication process of concrete/cement, the equipment may fail and compromise the appropriate mixing procedure. Besides that, it is also important to determine the right point of homogeneity of the mixture.
Roos Sophia Dam, Caroline M. Barbosa, José M. Lopes, Jardel L. Thalhofer, Leandro B. Silva, César M. Salgado, Ademir X. da Silva   +6 more
openaire   +1 more source

A Neutronic Evaluation of the HTR-10 Using Scale, MCNPX and MCNP5 Nuclear Codes

Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, 2014
The HTR-10 (High Temperature Gas-cooled Test Reactor) is a 10 MW modular pebble bed type reactor, built by the Institute of Nuclear Energy Technology (INET), Tsinghua University, China. As an advanced reactor, it has good passive safety characteristics: capacity of retaining all fission products inside the coated particles (up to 1,600° C), passive ...
Rômulo V. Sousa, Clarysson A. M. Silva, Ângela Fortini, Cláubia Pereira, Maria Auxiliadora F. Veloso, Antonella L. Costa   +5 more
openaire   +1 more source

A comparative study on shielding properties of some composite materials by MCNPX code

2019
The radiation mass attenuation coefficients of composite material samples as shielding materials have been calculated at 356, 511, 662, 1173, 1274 and 1332 keV photon energies by using general purpose Monte Carlo code MCNPX (version 2.6.0). The obtained numerical results agree well with experimental and standard XCOM data.
Altunsoy, Elif Ebru, TEKİN, HÜSEYİN OZAN, Singh, V. P., KARA, Ümit, AKKURT, İskender   +4 more
openaire   +1 more source

SPENT FUEL POOL CRITICALITY ANALYSIS THROUGH MCNPX 2.6.0 CODE

Anais da Semana Nacional de Engenharia Nuclear e da Energia e Ciências das Radiações, 2022
Jean A. D. Salomé, Clarysson A. M. da Silva, Raphael H. M. Silva, Cláubia Pereira   +3 more
openaire   +1 more source

Calculation of the gamma radiation shielding efficiency of cement-bitumen portable container using MCNPX code

Progress in Nuclear Energy, 2021
Sonia M Reda, Hosam M Saleh
exaly  

Radiation shielding features using MCNPX code and mechanical properties of the PbO Na2O B2O3CaO Al2O3SiO2 glass systems

Composites Part B: Engineering, 2019
Shams A M Issa, Yasser B Saddeek, M I Sayyed   +2 more
exaly  

Prediction of 94mTc production for positron emission tomography studies using the Monte Carlo code MCNPX-2.6

Applied Radiation and Isotopes, 2013
, H Afarideh, Claudio Tenreiro
exaly  

Implementation of a dynamic Monte Carlo method for transients analysis with thermal-hydraulic feedbacks using MCNPX code

Annals of Nuclear Energy, 2019
Naser Vosoughi
exaly