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Showing 1 to 20 of 68 for “"fusion reactor"”.

  1. 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

    uiuc Repository record for Liquid lithium corrosion studies for nuclear fusion reactor materials (opens in a new tab)

  2. 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) …

    cambridge Repository record for Next Generation Algorithms for Magnetically Confined Fusion Reactor Simulations (opens in a new tab)

  3. 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 …

    aston Repository record for Elastic and inelastic scattering of fast neutrons in fusion reactor materials (opens in a new tab)

  4. 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

    uiuc Repository record for Design and Engineering of Advanced Fuel Fusion Reactor First Wall Systems (opens in a new tab)

  5. Study of advanced railgun hydrogen pellet injectors for fusion reactor refueling

    … prevents high-Z impurities from entering the reactor during pellet injection.

    uiuc Repository record for Study of advanced railgun hydrogen pellet injectors for fusion reactor refueling (opens in a new tab)

  6. 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 …

    vt Repository record for Dynamical equilibrium and stability of a D-T fueled fusion reactor (opens in a new tab)

  7. A passively-safe fusion reactor blanket with helium coolant and steel structure

    Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1994.

    mit Repository record for A passively-safe fusion reactor blanket with helium coolant and steel structure (opens in a new tab)

  8. 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 …

    oviedo Repository record for Methodology for electromagnetic analysis using the finite element method for fusion reactor components (opens in a new tab)

  9. 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 …

    mit Repository record for A steady-state L-mode tokamak fusion reactor : large scale and minimum scale (opens in a new tab)

  10. 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 …

    mit Repository record for Design of demountable toroidal field coils with REBCO superconductors for a fusion reactor (opens in a new tab)

  11. 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 …

    mit Repository record for Design and construction of high-temperature, high-vacuum tensile tester for fusion reactor materials (opens in a new tab)

  12. 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 …

    mit Repository record for Analysis of damage mechanisms in boronized TZM tiles from Alcator C-Mod fusion reactor operations (opens in a new tab)

  13. 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 …

    mit Repository record for Investigation of sub-meter shields for a low aspect ratio D-T Tokamak fusion reactor (opens in a new tab)

  14. 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

    uiuc Repository record for Liquid Metal Waterfall Engineering in an Inertial confinement Fusion Reactor System Using Internal Tritium Breeding Pellets (opens in a new tab)

  15. 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 …

    must-thes Repository record for USING COMPUTATIONAL METHODS TO OPTIMIZE HIGH HEAT FLUX COMPONENT THERMAL PERFORMANCE IN MAGNETIC CONFINEMENT FUSION REACTOR RESEARCH (opens in a new tab)

  16. 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 …

    mit Repository record for Investigation of cryogenic cooling for a high-field toroidal field magnet used in the SPARC fusion reactor design (opens in a new tab)

  17. 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 …

    cape-town Repository record for Moderation of high-energy fast neutrons in beryllium from a tokamak fusion reactor and heat transfer to the cooling water system (opens in a new tab)

  18. 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 …

    uiuc Repository record for Deciphering the role of dispersoids in dispersion-strengthened tungsten alloys on the mechanical properties and irradiation- driven response under nuclear fusion reactor-relevant conditions (opens in a new tab)

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