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Showing 1 to 20 of 129 for “"Thermal Hydraulic"”.
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Thermal/hydraulic analysis methods for PWR's
Thesis. 1976. Nucl.E.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering.
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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 …
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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 …
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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 …
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Thermal-hydraulic analysis of tight lattice light water reactors.
Thesis. 1977. M.S.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering.
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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 …
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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: …
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Two dimensional transport coefficients for the PWR's thermal/hydraulic analysis.
Thesis. 1976. M.S.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering.
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Thermal hydraulic mixing transients in the MIT research reactor core tank
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1996.
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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 …
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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 …
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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 …
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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 …
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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 …
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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 …
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Multiscale approach for the thermal-hydraulic analysis of heavy liquid metal pool systems
L'abstract è presente nell'allegato / the abstract is in the attachment
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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 …
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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 …
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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 …
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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.
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