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Showing 1 to 20 of 129 for “"Thermal Hydraulic"”.

  1. Thermal/hydraulic analysis methods for PWR's

    Thesis. 1976. Nucl.E.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering.

    mit Repository record for Thermal/hydraulic analysis methods for PWR's (opens in a new tab)

  2. Thermal hydraulic analysis of hydride fuels in BWR's

    … More specifically, this thesis deals with the thermal hydraulic analysis of BWR reactors. Several papers and theses have already been written for this project, mainly focusing on PWR reactors. The primary goal of this thesis is to find the optimal fuel rod lattice pitch and diameter such that a …

    mit Repository record for Thermal hydraulic analysis of hydride fuels in BWR's (opens in a new tab)

  3. Thermal Hydraulic numerical analysis of Fusion superconducting magnet systems

    … such situations, it is essential to study thermal hydraulics and hence system code is needed for the whole superconducting magnet system. For such purposes, Cryogenic Circuit, Conductor and Coil code (4C) was built, imbibing the thermal hydraulic modeling of the cable in Conduit conductors …

    poli-torino Repository record for Thermal Hydraulic numerical analysis of Fusion superconducting magnet systems (opens in a new tab)

  4. Steady state thermal hydraulic analysis of hydride fueled BWRs

    … the main body of the analysis account only for thermal-hydraulic constraints, an estimate of the power reduction due to the application of neutronic constraints is also performed. This investigation, focused only on the "New Core" cases, is coupled with an increase of the thickness of the gap …

    mit Repository record for Steady state thermal hydraulic analysis of hydride fueled BWRs (opens in a new tab)

  5. Thermal-hydraulic analysis of tight lattice light water reactors.

    Thesis. 1977. M.S.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering.

    mit Repository record for Thermal-hydraulic analysis of tight lattice light water reactors. (opens in a new tab)

  6. Thermal-hydraulic analysis of a spectral shift reactor core

    … program has been developed which performs a thermal-hydraulic analysis of a mechanical spectral shift reactor fuel assembly. In this reactor type, the fuel to water volume ratio is changed to shift the neutron energy spectrum and control reactivity. The ability to handle different fuel to …

    vt Repository record for Thermal-hydraulic analysis of a spectral shift reactor core (opens in a new tab)

  7. Thermal Hydraulic Design of a Temperature Controlled Materials Irradiation Facility

    Made available in DSpace on 2017-07-06T18:55:13Z (GMT). No. of bitstreams: 3 Malone_George_J_MS.pdf: 39166083 bytes, checksum: a903041edb195813700e77f06eb49ceb (MD5) Malone_George_J_MS_ABS.pdf: 529193 bytes, checksum: 1783a6db3c70fc68a04c3b838ba95ef4 (MD5) license.txt: 4813 bytes, checksum: …

    uiuc Repository record for Thermal Hydraulic Design of a Temperature Controlled Materials Irradiation Facility (opens in a new tab)

  8. Two dimensional transport coefficients for the PWR's thermal/hydraulic analysis.

    Thesis. 1976. M.S.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering.

    mit Repository record for Two dimensional transport coefficients for the PWR's thermal/hydraulic analysis. (opens in a new tab)

  9. Thermal hydraulic mixing transients in the MIT research reactor core tank

    Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1996.

    mit Repository record for Thermal hydraulic mixing transients in the MIT research reactor core tank (opens in a new tab)

  10. Thermal hydraulic performance analysis of a small integral pressurized water reactor core

    A thermal hydraulic analysis of the International Reactor Innovative and Secure (IRIS) core has been performed. Thermal margins for steady state and a selection of Loss Of Flow Accidents have been assessed using three methodologies to account for uncertainty. thermal margin for steady state …

    nps Repository record for Thermal hydraulic performance analysis of a small integral pressurized water reactor core (opens in a new tab)

  11. Advanced thermal hydraulic simulations for human reliability assessment of nuclear power plants

    … understanding of the magnitude of the effect of thermal hydraulic (TH) uncertainties upon the failure probabilities of the operator actions of nuclear units. I demonstrate in this work that there is an effect of TH uncertainties on the operating crew's probability of recognizing errors during a …

    mit Repository record for Advanced thermal hydraulic simulations for human reliability assessment of nuclear power plants (opens in a new tab)

  12. Thermal hydraulic design of a salt-cooled highly efficient environmentally friendly reactor

    A 1 OOOMWth liquid-salt cooled thermal spectrum reactor was designed with a long fuel cycle, and high core exit temperature. These features are desirable in a reactor designed to provide process heat applications such as oil refinery needs of heat and electricity. The reactor uses the binary salt …

    mit Repository record for Thermal hydraulic design of a salt-cooled highly efficient environmentally friendly reactor (opens in a new tab)

  13. Thermal-hydraulic analysis of innovative fuel configurations for the sodium fast reactor

    … interaction (FCCI) for metallic fuel, cladding thermal and irradiation strain, the fuel melting point, sodium boiling, and to a lesser extent the sodium pressure drop in the fuel channels. Therefore, innovative fuel configurations that reduce clad stresses, sodium pressure drops, and fuel/clad …

    mit Repository record for Thermal-hydraulic analysis of innovative fuel configurations for the sodium fast reactor (opens in a new tab)

  14. Monte Carlo and thermal hydraulic coupling using low-order nonlinear diffusion acceleration

    … 10. Realistic reactor calculations also require thermal hydraulic (TH) feedback which was integrated into the source convergence process. The use of CMFD in addition to TH reduced the number of fission source generations by a factor of 3. Further reduction was achieved by performing nonlinear …

    mit Repository record for Monte Carlo and thermal hydraulic coupling using low-order nonlinear diffusion acceleration (opens in a new tab)

  15. Thermal hydraulic performance analysis of a small integral pressurized water reactor core

    A thermal hydraulic analysis of the International Reactor Innovative and Secure (IRIS) core has been performed. Thermal margins for steady state and a selection of Loss Of Flow Accidents have been assessed using three methodologies to account for uncertainty. The thermal hydraulic analysis has …

    mit Repository record for Thermal hydraulic performance analysis of a small integral pressurized water reactor core (opens in a new tab)

  16. Thermal-hydraulic optimization for high production of low-enriched uranium based molybdenum-99

    … model, calibrated numerically, is created to hydraulically and thermally model the coolant flow through the current reactor setup. Using flow network modeling (FNM), this analytic model is expanded to analyze other potential geometries that could maximize heat transfer. The findings show that …

    missouri Repository record for Thermal-hydraulic optimization for high production of low-enriched uranium based molybdenum-99 (opens in a new tab)

  17. Thermal-hydraulic characterization of single- and two-phase immersion cooling for electronic modules

    … systems has created severe challenges for thermal management. High-performance processors, power electronics, and dense printed circuit board (PCB) assemblies routinely dissipate heat fluxes that exceed the capabilities of conventional air-cooled heat sinks and even many single-phase liquid …

    uiuc Repository record for Thermal-hydraulic characterization of single- and two-phase immersion cooling for electronic modules (opens in a new tab)

  18. Thermal-hydraulic analysis of cross-shaped spiral fuel in high power density BWRs

    … spiral (CSS) fuel assembly suggests great thermal-hydraulic upside. According to computational models, the increase in rod surface area, combined with an increase in coolant turbulence and inter-channel mixing will allow for a greater than 25% uprate in total core power, without loss of …

    mit Repository record for Thermal-hydraulic analysis of cross-shaped spiral fuel in high power density BWRs (opens in a new tab)

  19. Reactor thermal-hydraulic analysis improvement and application of the code COBRA-IIIC/MIT

    Thesis (Nucl.E.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1981.

    mit Repository record for Reactor thermal-hydraulic analysis improvement and application of the code COBRA-IIIC/MIT (opens in a new tab)

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