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Showing 1 to 20 of 29 for “"MCNPX"”.
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Radiation shielding calculations by means of MCNPX
Monte Carlo radiation transport calculations were performed to re-evaluate the configuration of the horizontal target bombardment station of the ra-dionuclide production at iThemba LABS. Calculated neutron and photon dose attenuation factors for this shield were compared with those previously …
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Benchmarking photoneutron production of Mcnpx simulations with experimental results
… accelerator to a subcritical reactor assembly. MCNPX, a radiation transport code developed at the Los Alamos National Laboratory, was used in this study. The MCNPX predictions of photo-neutron production were compared with experimental results performed at Idaho Accelerator Centre (IAC), and …
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Radiation Shielding calculations using MCNPX transport code for cost optimization of the shielding material to be used at iThemba LABS.
… The Monte Carlo for Neutral Particles eXtended (MCNPX) code was used for the purpose of investigating the correct thickness of the shielding of the cyclotron vault and the RIB Demonstrator vault. Results obtained confirmed that 4m and 3m thicknesses of concrete shielding will be adequate in the …
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Speedup of MCNP(X) parallel KCODE execution via communication algorithm development and Beowulf Cluster optimization
… algorithm in MCNP. A new patch for the parallel MCNPX KCODE communication algorithm is examined. The new patch facilitates the local execution of KCODE cycles, greatly eliminating interprocess communication. Combined with numerous minor changes to MCNPX the new patch file can speed up MCNPX KCODE …
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Novel techniques for the detection and localization of attenuated gamma-ray sources
… Alamos Monte Carlo N-Particle transport code (MCNPX) for detector efficiency calculations. As a necessary supplement to the process, a program was written to automate all MCNPX simulations by modifying input cards and recording the results for all required scenarios. In this work, simulated …
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Measurement of spallation residuals in mercury for accelerator facility targets
… compared with predicted cross sections from the MCNPX code. After acquisition of the gamma spectroscopy data the targets were drained and disassembled to study the distribution and the deposition of the spallation residuals.
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Determination of energy spectra of proton therapy beams
… of the spectra were computed with the MCNPX 2.1.5 Monte Carlo code to compare with experimental measurements.
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SIMULATIONS OF SPACE RADIATION INTERACTIONS WITH MATERIALS, WITH APPLICATION TO DOSE ESTIMATES FOR LUNAR SHELTER AND ABOARD THE INTERNATIONAL SPACE STATION
… GCRs particles interactions are simulated using MCNPX and PHITS probabilistic codes. The energy loss and energy deposition within the shielding materials and in a phantom are calculated. The contributions of secondary particles produced by spallation reactions are identified. Recent experimental …
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Feasibility Study of a Natural Uranium Neutron Spallation Target using FLiBe as a Coolant
… The study utilized two different software tools, MCNPX 2.6 and FLUENT 12.1. MCNPX was used to determine the neutronics and heat deposited in the spallation target structure while FLUENT was used to determine the feasibility of cooling the target structure with FLiBe. Several target structures were …
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Fuel Cycle Modeling Improvements and Multi-Tiered Recycling With A Sodium-Cooled Heterogeneous Innovative Burner Reactor
… by modifying the CINDER90 depletion code used by MCNPX 2.6.0 to include helium production from α-decay. It was tested using the Sodium-Cooled Heterogeneous Innovative Burner Reactor (SCHIBR) model created at the University of South Carolina. Following gas production analysis, an innovative …
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On the integration of Computational Fluid Dynamics (CFD) simulations with Monte Carlo (MC) radiation transport analysis
… are employed for the CFD simulations while MCNPX is used for the MC Radiation Transport simulations.
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Evaluation of Presage® Dosimeters For Brachytherapy Sources and The 3D Dosimetry and Characterization of The New Agx100 125I Seed Model
… measured for the AgX100 agreed with the MCNPX and TLD-measured values within 3% in the r=1 to r=3 cm region. The measured anisotropy function in PRESAGE<sup>®</sup> showed relative differences of up to 9% with the MCNPX calculated values. It was determined that post-irradiation optical …
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Encapsulated source contact dose estimates incorporating secondary electron emission
… with the Monte Carlo radiation transport code MCNPX. Emission intensities were measured at the surface of source encapsulation and at increasing distances in tissue equivalent material. It is shown that the results obtained correlate to the historical trends, however the electron component of …
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Behavior and measurement of distributed sources in a shielding matrix using gamma spectroscopy
… noted, and then evaluated through modeling using MCNPX to determine the cause of the observed discrepancies.
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Determination of neutron energy spectra inside a water phantom irradiated by neutrons of energy up to ~ 64 Me V
… compare well with Monte Carlo calculations using MCNPX.
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Characterization of neutron fields around an intense neutron generator
… generator facility has been simulated using MCNPX 2.7E Monte Carlo particle transport program. The P-385 neutron generator is configured to function with a deuterium-deuterium fusion reaction using accelerated charged deuterons colliding with a metal deuteride target. This fusion reaction is …
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Evaluation of fast neutron shielding effectiveness in light-element compounds
… generator at 106 n/s intensity along with MCNPX and PHITS code simulations. The transmission factor in different experiments was found to vary from 11% up to 34% with increasing thickness. Simulation results were in reasonable agreement with experimental data and supported the conclusion …
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Study of space-time evolution of flux in a long-life traveling wave reactor
Simulations using MCNPX have been carried out to analyze the space and time evolution of flux in a Traveling Wave Reactor under constant thermal power condition. For the analyses of flux shape, a 3-D box-shaped model of the reactor is developed. The reactor core is divided into two primary regions: …
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Technical basis for use of a correlated neutron source in the uranium neutron coincidence collar
… the UNCL using Monte Carlo N-Particle Extended (MCNPX), version 2.7.4.a; (2) fully characterizes the detection parameters, including the efficiency profile, die-away time, and deadtime parameters; and (3) demonstrates the technical basis for the replacement of 241AmLi sources with 252Cf sources …
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Optimization of detector response simulations for multiple particles created by neutron-induced reactions
… normal and cancerous tissues. Based on the MCNPX simulations, the initial research focused on optimizing the yield of thermal neutrons in the PNF system, which can then be used as a source for the interactions with the biological sample while minimizing the background radiations. Moderating …
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