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.
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Showing 1 to 20 of 26 for “"reactor analysis"”.
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Spatial homogenization methods for light water reactor analysis
Thesis (Ph.D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1980.
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Developments in nodal reactor analysis tools for hexagonal geometry
A new nodal method for the solution of multigroup multidimensional diffusion problems in hexagonal geometry is developed and implemented into the FORTRAN code HEXPEDITE. The algorithm is adapted for modern computer features including vector and concurrent computations and demonstrates high …
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Novel Resonance Self-Shielding Methods for Nuclear Reactor Analysis
… of the behavior of neutrons in a nuclear reactor, there has long been a dichotomy in solution techniques. One can use Monte Carlo methods, known to be very accurate and problem agnostic but also very costly, or deterministic methods, known to be more computationally efficient but also …
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A quasi-static polynomial nodal method for nuclear reactor analysis
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1992.
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Discontinuous space-time dependent nodal synthesis method for reactor analysis
Thesis (M. Eng.)--Massachusetts Institute of Technology, Dept. of Electrical Engineering and Computer Science, 1996.
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Advanced application of the discrete generalized multigroup method and recondensation to reactor analysis
Fine-group whole-core reactor analysis remains one of the long sought goals of the reactor physics community. Such a detailed analysis is typically too computationally expensive to be realized on anything except the largest of supercomputers. Recondensation using the Discrete Generalized Multigroup …
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Numerical stability of Monte Carlo neutron transport and isotopic depletion for nuclear reactor analysis
… known to produce non-physical results for large reactor geometries. This thesis begins with a survey of the stable methods used to avoid this and highlights some of their drawbacks. Chapter 2 introduces the known phenomenon of neutron clustering in Monte Carlo as a factor strongly contributing to …
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Used Nuclear Fuel Actinide Management in a Sodium- Cooled Heterogeneous Innovative Burner Reactor
… a design of an innovative sodium-cooled fast reactor (SFR) for minor actinide (MA) destruction in used nuclear fuel (UNF). The destruction of MAs would reduce the radiotoxicity of the discharged waste to less than 25% of the once-through cycle after 100 years. The design can be achieved within …
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Domain decomposition for Monte Carlo particle transport simulations of nuclear reactors
… as we move towards higher-fidelity nuclear reactor analyses the method has become competitive with traditional deterministic transport algorithms for the same level of accuracy, especially considering the inherent parallelism of the method and the ever-increasing concurrency of modern high …
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Part One: A Flow Reactor With In-Line Analytics: Design and Implementation Part Two: In-Line Derivatization of Protic Compounds for GC/MS Reaction Monitoring
… First, the design and implementation of a flow reactor system complete with in-line gas chromatography mass spectrometry (GC/MS) analytical instrument is discussed. The testing and validation of the systems components was completed in order to create a fully automated chemical reaction system …
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A study of turbulent mass transfer in a wetted-wall column
… extraction, absorption, adsorption, and reactor analysis and design.</p> <p>However, much of the knowledge in this area at the present time is in the form of empirical relationships, and the basic theory is still not well delineated. This lack of understanding leads to expensive and …
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Measurement of Liquid Film in Annular Flow Using X-Ray Densitometry
… more reliable film thickness data for improved reactor safety calculations in Boiling Water Reactors (BWR), Pressurized Water Reactors (PWR), and accident scenarios such as Loss of Coolant Accidents (LOCA), where accurate film thickness data is essential for reliable predictions in reactor …
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Nuclear reactor multiphysics via bond graph formalism
… and effective approach to modeling nuclear reactor multiphysics problems using bond graphs. Conventional multiphysics simulation paradigms normally use operator splitting, which treats the individual physics separately and exchanges the information at every time step. This approach has …
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Monte Carlo and thermal hydraulic coupling using low-order nonlinear diffusion acceleration
Monte Carlo (MC) methods for reactor analysis are most often employed as a benchmark tool for other transport and diffusion methods. In this work, we identify and resolve a few of the issues associated with using MC as a reactor design tool. It is widely thought that MC tallies converge at an ideal …
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Space-Time Kinetics of the AGN-201M Research Reactor at the University of New Mexico
… measurements were performed on the AGN- 201M reactor (AGN) at the University of New Mexico. Steady-state measurements were made with the AGN in various delayed critical configurations. These delayed critical configurations are defined by moving the coarse and fine control rods to unique …
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Exocellular Polymeric Substances, Bioflocculation and Sludge Settling Properties in a Combined Anaerobic/Activated Sludge Process
… from the sludge produced in the anaerobic reactor. Analysis of the data showed that the combined system proved to be unstable producing unexpected results such as no clear relationship between MLVSS and EPS. For a DO of zero, no EPS are produced and no flocculation takes place; therefore, …
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Parallel algorithms for Monte Carlo particle transport simulation on exascale computing architectures
… option for high-fidelity simulation of nuclear reactors. While Monte Carlo methods offer several potential advantages over deterministic methods, there are a number of algorithmic shortcomings that would prevent their immediate adoption for full-core analyses. In this thesis, algorithms are …
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Acceleration methods for Monte Carlo particle transport simulations
Performing nuclear reactor core physics analysis is a crucial step in the process of both designing and understanding nuclear power reactors. Advancements in the nuclear industry demand more accurate and detailed results from reactor analysis. Monte Carlo (MC) eigenvalue neutron transport methods …
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Improvements and applications of the Uniform Fission Site method in Monte Carlo
Monte Carlo methods for reactor analysis have been in development with the eventual goal of full-core analysis. To attain results with reasonable uncertainties, large computational resources are needed. Variance reduction methods have been developed in order to reduce the computational resources …
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