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Now showing items 3981-3990 of 4142
Thermohydraulics and suppression of nucleate boiling in upward two-phase annular flow : probing multiscale physics by innovative diagnostics
(Massachusetts Institute of Technology, 2018)
In the fuel assemblies of a boiling water reactor (BWR) the steam quality increases along the assembly's length as heat is transferred from the fuel rods to the water coolant. Nucleate boiling is the dominant heat transfer ...
Studies on hydration water dynamics and microstructure of synthetic cement
(Massachusetts Institute of Technology, 2017)
The mechanical properties of cement pastes depend strongly on their porosities. In a wet paste, the porosity links to the free water volume after hydration. Structural water which presents in the solid phase, constrained ...
Experimental study of heat flux partitioning in pressurized subcooled flow boiling
(Massachusetts Institute of Technology, 2018)
Understanding of subcooled flow boiling and the critical heat flux (CHF) is of the utmost importance for both safety and profitability of pressurized water nuclear reactors since they are major factors in the determination ...
Detection of lower hybrid waves at the plasma edge of a diverted tokamak
(Massachusetts Institute of Technology, 2014)
In this thesis, two experimental investigations are presented in an attempt to understand the loss of lower hybrid current drive (LHCD) efficiency in reactor-relevant, high-density plasmas on the diverted Alcator C-Mod ...
Quantum assisted sensing, simulation and control
(Massachusetts Institute of Technology, 2016)
This thesis describes experimental and theoretical work making contributions with the aims of improving and advancing techniques of quantum metrology, simulation and control. Towards this goal, we engineer novel devices ...
Prediction of departure from nucleate boiling in subchannel applications : from mechanistic modeling to hybrid framework
(Massachusetts Institute of Technology, 2019)
The critical heat flux (CHF) corresponding to the departure from nucleate boiling (DNB) is a regulatory limit for licensing of pressurized water reactors (PWRs). Under DNB conditions, the heated surface is blanketed by a ...
Accelerated atomistic prediction of structure, dynamics and material properties in molten salts
(Massachusetts Institute of Technology, 2020)
Various advanced nuclear reactors including fluoride high-temperature salt-cooled reactors (FHRs), molten salt reactors (MSRs) and fusion devices have proposed to use molten salt coolants. However, there remain many ...
Characterization of a turbulence bifurcation underlying L-mode confinement transitions on Alcator C-Mod
(Massachusetts Institute of Technology, 2020)
Empirical energy confinement scalings play a crucial role in the design of tokamak fusion reactors, measuring how quickly energy is transported by turbulence from the fusion-producing core to conduction loss at the edge. ...
Tritium retention in nuclear graphite, system-level transport, and management strategies for the fluoride-salt-cooled high-temperature reactor
(Massachusetts Institute of Technology, 2021)
Advanced reactor concepts which use a lithium- or beryllium-bearing primary salt coolant will require technical solutions to mitigate the environmental release of tritium. One such design is the Fluoride-Salt-Cooled ...
Cumulative migration method for computing multi-group transport cross sections and diffusion coefficients with Monte Carlo calculations
(Massachusetts Institute of Technology, 2020)
In nuclear reactor physics analysis, fast accurate deterministic methods are needed for the many full-core calculations required for safe and efficient operation of nuclear power plants. Multi-group diffusion coefficients ...