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Showing 1 to 4 of 4 for “"Monte Carlo N-Particle Transport Code (MCNP)"”.
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Characterization of the Neutron Irradiation System for use in the Low-Dose-Rate Irradiation Facility at Sandia National Laboratories
… of the source and shielding was modeled using Monte Carlo N-Particle transport code (MCNP). The model was validated by benchmarking it against measurements using multiple techniques. To characterize the radiation fields over the full spatial geometry of the irradiation system, it was necessary …
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Impact of thorium based molten salt reactor on the closure of the nuclear fuel cycle
… to achieve this objective, the applicability of Monte Carlo N-Particle Transport Code (MCNP) to MSR modeling was verified. Then, a prescription for conceptual small thermal reactor LFTR and relevant calculations were performed using MCNP to determine the main neutronic parameters of the core …
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MCODE-3 : time-dependent depletion isotopics with MCNP-5 and SCALE-6.1
… environment, a time-dependent depletion isotopic code must be used. Over the past several decades, the MIT Reactor (MITR) has taken many steps to prepare for its conversion from the use of highly enriched uranium (HEU) to low enriched uranium (LEU) in its fuel. Throughout this process, detailed …
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Comprehensive fuel performance model development and simulation for triso fuel
Item withdrawn by Alexis Thompson (athmpsn1@illinois.edu) on 2011-01-13T19:58:31Z Item was in collections: University of Illinois Theses & Dissertations (ID: 1) No. of bitstreams: 1 Hu_Jianwei.pdf: 5191894 bytes, checksum: 702afe062ec7e3d71c3ef29c7b15f21a (MD5)