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Showing 1 to 6 of 6 for “"MCNP/X"”.
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Speedup of MCNP(X) parallel KCODE execution via communication algorithm development and Beowulf Cluster optimization
This thesis examines two methods for speeding up MCNP KCODE calculations. The first approach is assembly of a low cost Beowulf Cluster for parallel computation. The first half describes the MIT Nuclear Engineering Department's Beowulf Cluster, Echelon, as a prototype. Echelon is a low cost, 30 …
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Optimization of plastic scintillator thicknesses for online beta detection in mixed fields
… monitor. The simulation has been performed using MCNP/X code and different thicknesses of plastic scintillators ranging from 150 to 600 um have been used. The relationship between the thickness of the scintillator and the efficiency of the detector has been analyzed. For 150 m thickness, an …
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Study of LaBr3 (Ce) detector response to high energy helium ions
… A series of Monte-Carlo simulations using MCNP/X version 2.6 have been performed along with a series of experiments using the Heavy Ion Medical Accelerator in Chiba, Japan. Measurements of the detector response function were conducted using He ion beams at various energies.
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Development of neutron monitor for fusion systems
… Carlo simulations have been performed using MCNP/X along with a series of experiments carried out using a neutron generator based on the (D, D) reaction at 106 n/s. Both sets of data were compared in term of the pulse height spectra. The analysis of the data suggests that a prominent peak …
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Design and optimization of a multi-particle accelerator beam transport and delivery system for material irradiation in nuclear and fusion science
… designed using SolidWorks and calculated with MCNP/X The design specification of M2TF with respect to beam energy, current density, and control were achieved based on these design tools and previously developed analytic methods. The design process for the cyclotrons resulted in a 4.3T …
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Development and characterization of a high resolution portable gamma spectrometer
… been modeled using advanced Monte Carlo code (MCNP/X code) for the response function simulation and parameter characterization. The simulation results have been validated by experimental investigations using a wide range of gamma radiation energies. The developed spectrometer has been …