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  • About
  • The Global ETD Search service is a free service for researchers to find electronic theses and dissertations. This service is provided by the Networked Digital Library of Theses and Dissertations.
    Our metadata is collected from universities around the world. If you manage a university/consortium/country archive and want to be added, details can be found on the NDLTD website.
471

Exploiting continuity-in-time in motion vision

Michael, David Joshua January 1992 (has links)
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1992. / Includes bibliographical references (leaves 81-87). / by David Joshua Michael. / Ph.D.
472

The effect of surface conditions on nucleate pool boiling heat transfer to sodium.

Marto, Paul James January 1965 (has links)
Massachusetts Institute of Technology. Dept. of Nuclear Engineering. Thesis. 1965. Sc.D. / Sc.D.
473

The treatment of uncertainties in the thermal design of nuclear reactors

Guéron, Henri Max January 1967 (has links)
Massachusetts Institute of Technology. Dept. of Nuclear Engineering. Thesis. 1967. Ph.D. / Bibliography: leaves 177-185. / by Henri M. Gueron. / Ph.D.
474

Plasma and neutral gas jet interactions in the exhaust of a magnetic confinement system

Krueger, Warren Allyn January 1990 (has links)
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1990. / Includes bibliographical references (p. 235-236). / by Warren Allyn Krueger. / Ph.D.
475

Measurement and interpretation of chemical and radiochemical data from PWR in-pile loop runs

Zhang, Michael Ming-Ruo January 1991 (has links)
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1991. / Includes bibliographical references (leaves 121-123). / by Michael Meng-Ruo Zhang. / M.S.
476

Liquid droplet trajectories in two-phase flow.

Farmer, Richard Albert January 1969 (has links)
Massachusetts Institute of Technology. Dept. of Nuclear Engineering. Thesis. 1969. Ph.D. / Vita. / Bibliography: leaves 204-206. / Ph.D.
477

Exclusion area radiation release during the MIT reactor design basis accident

Mull, Robert F January 1983 (has links)
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1983. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE / Includes bibliographical references. / by Robert Forrest Mull. / M.S.
478

Constraints on the scale of toroidal fusion experiments with application to the design of a helical axis stellarator

Noterdaeme, Jean-Marie André January 1983 (has links)
Thesis (Ph.D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1983. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE / Includes bibliographical references. / by Jean-Marie Noterdaeme. / Ph.D.
479

Design, analysis and optimization of the power conversion system for the Modular Pebble Bed Reactor System / Power conversion system for the MPBR

Wang, Chunyun, 1968- January 2003 (has links)
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2003. / Includes bibliographical references. / This electronic version was submitted by the student author. The certified thesis is available in the Institute Archives and Special Collections. / The Modular Pebble Bed Reactor system (MPBR) requires a gas turbine cycle (Brayton cycle) as the power conversion system for it to achieve economic competitiveness as a GenIV nuclear system. The availability of controllable helium turbomachinery and compact heat exchangers are thus the critical enabling technology for the gas turbine cycle. The development of an initial reference design for an indirect helium cycle has been accomplished with the overriding constraint that this design could be built with existing technology and complies with all current codes and standards. Using the initial reference design, limiting features were identified. Finally, an optimized reference design was developed by identifying key advances in the technology that could reasonably be expected to be achieved with limited R&D. This final reference design is an indirect, intercooled and recuperated cycle consisting of a three-shaft arrangement for the turbomachinery system. A critical part of the design process involved the interaction between individual component design and overall plant performance. The helium cycle overall efficiency is significantly influenced by performance of individual components. Changes in the design of one component, a turbine for example, often required changes in other components. To allow for the optimization of the overall design with these interdependencies, a detailed steady state and transient control model was developed. The use of the steady state and transient models as a part of an iterative design process represents the key contribution of this work. A dynamic model, MPBRSim, has been developed. / (cont.) The model integrates the reactor core and the power conversion system simultaneously. Physical parameters such as the heat exchangers' weights and practical performance maps such as the turbine characteristics and compressor characteristics are incorporated into the model. The individual component models as well as the fully integrated model of the power conversion system have been verified with an industry-standard general thermal-fluid code Flownet. With respect to the dynamic model, bypass valve control and inventory control have been used as the primary control methods for the power conversion system. By performing simulation using the dynamic model with the designed control scheme, the combination of bypass and inventory control was optimized to assure system stability within design temperature and pressure limits. Bypass control allows for rapid control system response while inventory control allows for ultimate steady state operation at part power very near the optimum operating point for the system. Load transients simulations show that the indirect, three-shaft arrangement gas turbine power conversion system is stable and controllable. For the indirect cycle the intermediate heat exchanger (IHX) is the interface between the reactor and the turbomachinery systems. As a part of the design effort the IHX was identified as the key component in the system. Two technologies, printed circuit and compact plate-fin, were investigated that have the promise of meeting the design requirements for the system ... / by Chunyun Wang. / Ph.D.
480

Homogenization and dehomogenization schemes for BWR assemblies

Finck, Philippe Jean January 1983 (has links)
Thesis (Ph.D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1983. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE / Includes bibliographical references. / by Philippe Jean Finck. / Ph.D.

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