Global ETD Search
Search theses and dissertations gathered from participating repositories worldwide. Every result links back to the library that holds it. No account is needed.
Results
Showing 1 to 14 of 14 for “"MCNP5"”.
-
Nuclear reactor multi-physics simulations with coupled MCNP5 and STAR-CCM+
The MCNP5 Monte Carlo particle transport code has been coupled to the computational fluid dynamics code, STAR-CCM+, to provide a high fidelity multi-physics simulation tool for analyzing the steady state properties of a PWR core. The codes are executed separately and coupled externally through a …
-
Criticality alarm system design guide with accompanying alarm system development for the Radiochemical Processing Laboratory in Richland, Washington
… analysis for RPL utilized the Monte Carlo code MCNP5 for establishing detector coverage in the facility. Based on the design methodology, significant improvements to the existing CAS were made that increase the reliability, transparency, and coverage of the system.
-
A combined radiographic and time-of-flight method for zero-knowledge warhead verification
… level of information security. Results using a MCNP5¹ model of the verification setup on the "Black Sea Object" pit geometry as well as a speculative HEU implosion weapons design indicate that the method would be highly effective, even using existing research reactor or accelerator neutron …
-
Computational aspects of treatment planning for neutron capture therapy
… Monte Carlo radiation transport code MCNP5. The comparison of multidimensional dose data in the form of dose profiles, isodose contours, dose difference distributions and dose-volume histograms yielded many clinically significant differences. Additional calculations were performed to …
-
Characterization of the MIT Graphite Exponential Pile
… neutronic model of the pile was created using MCNP5 software and used to map the spatial source dependence. Experimental measurements were taken to compare to simulated model data and determine the accuracy of the model. The overall flux shapes were similar, but the error between the model …
-
Methods for optimization of the signature-based radiation scanning approach for detection of nitrogen-rich explosives
… were simulated and analyzed using the MCNP5 code. For each configuration, 51 different inert materials were used as inert samples and as clutter in front of the explosive cyclonite (RDX). The geometric configurations consisted of different explosive volumes, clutter thicknesses, and …
-
Facility-Specific Radiation Exposure Risks and Their Implications for Radiation Workers at Department of Energy Laboratories
… of exposure cases, creation and modification of MCNP5 models, development of a time-and-motion study, and the final synthesis of all data. This work also develops a new risk-based method of determining whether administrative controls, such as staffing increases, are ALARA-optimized. The EPAs …
-
Examining Thin Film AlSb for Room Temperature Gamma Detectors
… mobility. Simulations were performed using MCNP5 to predict energy deposited in AlSb by low energy gammas from Ba-133 and Co-57. A benchmark model was developed using a silicon surface barrier detector to validate AlSb simulations. Prior to radiation experiments, a series of characterization …
-
PREDICTING THE SENSITIVITY OF A BERYLLIUM/SCINTILLATOR FUSION NEUTRON DETECTOR COMBINING EXPERIMENTAL METHODS AND MONTE CARLO MODELS
… using NIST traceable beta and gamma sources and MCNP5 was used to model the energy deposition from each source. Combining the experimental and calculated results gives the desired empirical relationships. The results from this methodology were compared with previous work and the two results were …
-
Development of a Novel Detector Response Formulation and Algorithm in RAPID and its Benchmarking
… $2sigma$ relative statistical uncertainties of MCNP5 + CADIS (Consistent Adjoint Driven Importance Sampling) standard fixed-source calculation. The DRF methodology only requires order of seconds for the dosimeter/detector response or dose value calculations using 1 processor if the DRF …
-
A Novel Methodology for Iterative Image Reconstruction in SPECT Using Deterministic Particle Transport
… comparison with results from the SIMIND and MCNP5 Monte Carlo codes in this dissertation. The TITAN SPECT formulation has been improved through a modified collimator representation and full parallelization. The DRS methodology has been implemented in the TITAN code to create TITAN with Image …
-
ENVIRONMENTAL RADIATION DOSE ASSESSMENT AND VALIDATION FOR URANIUM HEXAFLUORIDE STORAGE MANAGEMENT
… 6.1.2 for source importance data generation, and MCNP5 (v1.60) for radiation dose calculations. The indirect Monte Carlo simulation process developed from Phase 3 was applied to a case study involving different storage configurations to investigate the dose trend and sensitivity to storage …
-
Neutronic Performance and Thermal Hydraulic Analysis of the MIT Reactor Fission Converter Experimental Facility Using High-Density U-10Mo Low-Enriched Uranium Fuel Elements
… facility have been performed using the codes MCNP5 and STAT7, respectively. This analysis quantified the FC’s k_eff, power distribution, multi-group neutron flux, and conditions which cause onset of nucleate boiling (ONB). It was determined that the FC assembly will remain subcritical (k _eff …
-
Multi-Purpose Research Reactor Designs Using MCNP and Origen
Made available in DSpace on 2017-07-06T18:48:39Z (GMT). No. of bitstreams: 3 Hu_Jianwei_MS.pdf: 12941059 bytes, checksum: bab58c978d20c697c63132361864a936 (MD5) Hu_Jianwei_MS_ABS.pdf: 35914 bytes, checksum: e11195f3129796aebd383242e916a02c (MD5) license.txt: 4813 bytes, checksum: …