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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 68 for “"fusion reactor"”.
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Liquid lithium corrosion studies for nuclear fusion reactor materials
Submission published under a 24 month embargo labeled 'U of I Access', the embargo will last until 2025-05-01
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Next Generation Algorithms for Magnetically Confined Fusion Reactor Simulations
… algorithms for whole-system nuclear fusion reactor simulations, with a focus on predicting and understanding non-linear MHD (magnetohydrodynamics) plasma instabilities and disruption events. The objective is to model all reactor regions (plasma, quasi-vacuum, and containment vessel) …
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Elastic and inelastic scattering of fast neutrons in fusion reactor materials
… and. inelastic scattering of fast neutrons in fusion .reactor materials have been studied. Lithium and lead material are likely to be common components of fusion reactor wall configuration design. The measurements were performed using an associated particle time-of- flight technique. The 14 and …
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Design and Engineering of Advanced Fuel Fusion Reactor First Wall Systems
Made available in DSpace on 2017-07-06T18:55:42Z (GMT). No. of bitstreams: 2 Olson_Richard_E_MS.pdf: 36443626 bytes, checksum: 495d7b0e83529c3ec6c15310fe3ee2d7 (MD5) license.txt: 4813 bytes, checksum: 715c4321821a960fa1a1e91d2ac7ebce (MD5) Previous issue date: 1979
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Study of advanced railgun hydrogen pellet injectors for fusion reactor refueling
… prevents high-Z impurities from entering the reactor during pellet injection.
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Dynamical equilibrium and stability of a D-T fueled fusion reactor
… were equal. A divertor was employed in the reactor to remove ions, alpha particles, and impurities. Equilibrium point solutions and fractional burn-ups were obtained after simulating different operating regimes of a D-T fueled fusion reactor. This was done essentially by varying a …
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A passively-safe fusion reactor blanket with helium coolant and steel structure
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1994.
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Methodology for electromagnetic analysis using the finite element method for fusion reactor components
En el diseño de componentes de reactores de fusión se realizan análisis electromagnéticos (EM) para verificar que soportan las cargas EM que surgen durante eventos de plasma transitorios, asegurando así su correcto funcionamiento. La metodología para la realización de análisis EM para componentes …
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A steady-state L-mode tokamak fusion reactor : large scale and minimum scale
… analysis on the physics of L-mode tokamak fusion reactors to identify (1) a favorable parameter space for a large scale steady-state reactor and (2) an operating point for a minimum scale steady-state reactor. The identification of the large scale parameter space is part of the 2008 MIT …
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Design of demountable toroidal field coils with REBCO superconductors for a fusion reactor
… be a revolutionary development for magnetic fusion. REBCO has significantly better performance at high magnetic fields than traditional low temperature superconductors (LTS), and can be operated at a higher temperature than LTS for reduced thermodynamic cost of cooling. Use of REBCO …
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Design and construction of high-temperature, high-vacuum tensile tester for fusion reactor materials
Fusion energy is a promising carbon-free, limitless source of energy that could contribute to mitigating global climate change. One of the critical challenges in realizing fusion energy is the survival of structural materials in the extreme environment of a fusion device. Specifically, materials …
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Analysis of damage mechanisms in boronized TZM tiles from Alcator C-Mod fusion reactor operations
Alcator C-Mod is a deuterium tokamak reactor experiment operated by the MIT Plasma Science and Fusion Center. Following the 2008 Alcator C-Mod campaign, the reactor was shut down and opened for maintenance and upgrades. During this time, it was discovered that the boronized TZM tiles, with boron …
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Investigation of sub-meter shields for a low aspect ratio D-T Tokamak fusion reactor
A significant effort is being made by fusion researchers to minimize the total size of magnetic fusion devices on the path toward developing fusion energy. The spherical tokamak, which has a very low aspect ratio, is the most promising of the compact magnetic fusion reactor designs. This …
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Liquid Metal Waterfall Engineering in an Inertial confinement Fusion Reactor System Using Internal Tritium Breeding Pellets
Made available in DSpace on 2017-07-06T18:42:11Z (GMT). No. of bitstreams: 2 Adams_Bradley_J_MS.pdf: 41791610 bytes, checksum: 39e215dbafc657c339c0b77672663b47 (MD5) license.txt: 4813 bytes, checksum: 715c4321821a960fa1a1e91d2ac7ebce (MD5) Previous issue date: 1983
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USING COMPUTATIONAL METHODS TO OPTIMIZE HIGH HEAT FLUX COMPONENT THERMAL PERFORMANCE IN MAGNETIC CONFINEMENT FUSION REACTOR RESEARCH
… to support experimental research for nuclear fusion applications. The project begins by designing and analyzing test sections supporting a helium flow loop assembled at Oak Ridge National Laboratory to analyze heat transfer enhancement for systems such as blanket and divertor components. This …
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Investigation of cryogenic cooling for a high-field toroidal field magnet used in the SPARC fusion reactor design
… highly compact, high-field SPARC Version 0 (V0) reactor design. The V0 design is set to operate at magnetic fields as high as 20 T, and operating temperatures ranging from 10-30 K. Due to the increase in range of operating conditions made available through the HTS-based magnets, a new set of …
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Mechanical Properties and Microstructure of Copper Alloys and Copper Alloy-Stainless Steel Laminates for Fusion Reactor High Heat Flux Applications
… precipitate morphology changes and interdiffusion of constituent elements.
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Moderation of high-energy fast neutrons in beryllium from a tokamak fusion reactor and heat transfer to the cooling water system
… primary neutrons in beryllium emitted from a D-T fusion nuclear reaction. The energy deposited from neutron-beryllium interactions which produces heat in the blanket of a fusion tokamak. A review of literature and data available for neutron-beryllium interactions is provided to support the MC …
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Deciphering the role of dispersoids in dispersion-strengthened tungsten alloys on the mechanical properties and irradiation- driven response under nuclear fusion reactor-relevant conditions
… components in future plasma- burning fusion reactors because of its high melting point, high sputter threshold, and low hydrogenic species retention. However, tungsten is an intrinsically brittle material, displaying no room temperature ductility and only exhibiting non-brittle failure …
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