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Characterization of a turbulence bifurcation underlying L-mode confinement transitions on Alcator C-Mod 

Cao, Norman Ming-Chen. (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. ...
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Investigation of Separate Effects of Surface Condition on Subcooled Flow Boiling Heat Transfer 

Seong, Jee Hyun (Massachusetts Institute of Technology, 2021-09)
In Pressurized Water Reactor (PWRs), heat generated by nuclear fissions is effectively transferred to the water coolant by subcooled flow boiling. The maximum reactor power is limited by the critical heat flux (CHF), at ...
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Prediction of departure from nucleate boiling in subchannel applications : from mechanistic modeling to hybrid framework 

Zhao, Xingang,Ph.D.Massachusetts Institute of Technology. (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 ...
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Measurements of divertor target plate conditions and their relationship to scrape-off layer transport 

Kuang, Adam QingYang. (Massachusetts Institute of Technology, 2019)
Cross-field filamentary transport in the scrape-off layer (SOL) is important for controlling SOL profiles, main-chamber recycling fluxes, and divertor operation. However, questions remain about the extent to which divertor ...
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Extending bubble-induced turbulence modeling applicability in CFD through incorporation of DNS understanding 

Magolan, Benjamin Lawrence (Massachusetts Institute of Technology, 2018)
Precise knowledge and understanding of the multiphase flow distribution is essential for light water reactor design. Multiphase Computational Fluid Dynamics (M-CFD) modeling and simulation techniques provide three-dimensional ...
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The role of grain boundary character in hydrogen embrittlement of nickel-iron superalloys 

Hanson, John Paul, Ph. D. Massachusetts Institute of Technology (Massachusetts Institute of Technology, 2016)
Hydrogen embrittlement of engineering alloys is characterized by a loss of ductility and unpredictable failure. These failures affect numerous industries, including nuclear power, oil and gas exploration, and hydrogen ...
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Full core 3D neutron transport simulation using the method of characteristics with linear sources 

Gunow, Geoffrey Alexander (Massachusetts Institute of Technology, 2018)
The development of high fidelity multi-group neutron transport-based simulation tools for full core Light Water Reactor (LWR) analysis has been a long-standing goal of the reactor physics community. While direct transport ...
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A methodology for modular nuclear power plant design and construction 

Lapp, Christopher Warren (Massachusetts Institute of Technology, 1989)
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On-the-fly nuclear data processing methods for Monte Carlo simulations of intermediate and fast spectrum systems 

Walsh, Jonathan A. (Jonathan Alan) (Massachusetts Institute of Technology, 2016)
Computational methods for on-the-fly representation and processing of nuclear data within Monte Carlo neutron transport simulations of intermediate and fast spectrum systems are developed and implemented in a continuous-energy ...
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Local transport analysis for the Alcator C-Mod tokamak 

Schachter, Jeffrey M (Massachusetts Institute of Technology, 1997)
Two complementary approaches were used to characterize transport on the Alcator C­Mod tokamak. The first was an empirical analysis of the scaling of transport with P*, the ion Larmor radius normalized to the plasma size. ...
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AuthorZhang, Yang (2)Zhang, Yi (2)Accorsi, Roberto, 1971- (1)Acton, Michael (Michael John) (1)Adams, Jacob (1)Adams, Mark Lloyd, 1972- (1)Adrian, Patrick J. (1)Advani, Rahul N (1)Agostinelli, Giulia. (1)Aguiar, Gustavo Matana (1)... View MoreDepartment
Department of Nuclear Science and Engineering (612)
Department of Nuclear Engineering (298)Center for Computational Science and Engineering (4)Health Sciences and Technology (1)Operations Research Center (1)Plasma Fusion Center (1)DegreePh.D. (433)Ph. D. (104)Sc.D. (56)Sc. D. (7)Ph. D. in Applied Plasma Physics (3)Ph. D. in Computational Nuclear Science and Engineering (3)Ph. D. in Quantum Science and Engineering (2)Ph. D. in Computational Nuclear Science & Engineering (1)Ph.D.cn (1)Ph.D.in Applied Plasma Physics (1)... View MoreSubjectNuclear Science and Engineering. (225)Nuclear Engineering. (160)Nuclear Engineering (156)Nuclear fuel elements (9)Boiling water reactors (4)Light water reactors (4)Neutron transport theory (4)Nuclear reactors Tables (4)Nuclear reactors Computer programs (3)Pressurized water reactors (3)... View MoreDate Issued2020 - 2025 (85)2010 - 2019 (154)2000 - 2009 (128)1990 - 1999 (137)1980 - 1989 (67)1970 - 1979 (22)1960 - 1969 (17)1959 - 1959 (2)Has File(s)Yes (612)

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