Recursos de colección

DSpace at MIT (104.280 recursos)

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Nuclear Engineering - Engineer's degree

Mostrando recursos 1 - 20 de 40

  1. Load following operation of a pressurized water nuclear power plant/

    Andrade, Gilberto Gomes
    by Gilberto Gomes De Andrade.

  2. Pipe wall damage morphology measurement methodology development for flow assisted corrosion evaluation

    Rangel, Julio Cesar Ferreira, 1963-
    by Julio Cesar Ferreira Rangel.

  3. CANDU pressure/calandria tube emergency water injection system

    Marques, Andre Luis Ferreira, 1963-
    by Andre Luis Ferreira Marquis.

  4. The finite element method applied to neutron diffusion problems.

    Deppe, Lothario Olavo
    Massachusetts Institute of Technology. Dept. of Nuclear Engineering. Thesis. 1973. Nucl.E.

  5. Sensitivity study of the assembly averaged thermal-hydraulic models of the MEKIN computer code in power transients

    Rodack, Thomas
    by Thomas Rodack.

  6. Uncertainty and sensitivity analysis of a fire-induced accident scenario involving binary variables and mechanistic codes

    Minton, Mark A. (Mark Aaron)
    In response to the transition by the United States Nuclear Regulatory Commission (NRC) to a risk-informed, performance-based fire protection rulemaking standard, Fire Probabilistic Risk Assessment (PRA) methods have been improved, particularly in the areas of advanced fire modeling and computational methods. As the methods for the quantification of fire risk are improved, the methods for the quantification of the uncertainties must also be improved. In order to gain a more meaningful insight into the methods currently in practice, it was decided that a scenario incorporating the various elements of uncertainty specific to a fire PRA would be analyzed. The NRC...

  7. Feasibility of lateral emplacement in very deep borehole disposal of high level nuclear waste

    Gibbs, Jonathan Sutton
    The U.S. Department of Energy recently filed a motion to withdraw the Nuclear Regulatory Commission license application for the High Level Waste Repository at Yucca Mountain in Nevada. As the U.S. has focused exclusively on geologic disposal in shallow mined repositories for the past two decades, an examination of disposal alternatives will be necessary should the Yucca Mountain Project be terminated. This provides an opportunity to study other promising waste disposal technologies. One such technology is the use of very deep boreholes in monolithic granite to permanently segregate high level wastes from the biosphere. While research in this field has...

  8. Design of a coordinated plant control system for a marine nuclear propulsion plant

    Baltra Aedo, Guillermo
    by Guillermo Baltra Aedo.

  9. Fuel element performance maps for nuclear reactor operational decisions.

    Da Silva, Othon Luiz Pinheiro
    Thesis. 1978. Nucl.E.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering.

  10. A study of US nuclear power boiling water reactor, class IV, operating performance, 1992-1997

    Brodeur, David Lester, 1963-
    by David Lester Brodeur.

  11. Molecular dynamics simulation studies of fracture in two dimensions

    De Celis, Benito
    by Benito de Celis.

  12. Evaluation of deep drillholes for high level nuclear waste disposal

    Kuo, Weng-Sheng
    by Weng-Sheng Kuo.

  13. Stability analysis of CICCs by measurement of energy deposition due to pulsed current disturbances

    Ahmed, Mustafa Kamal
    by Mustafa Kamal Ahmed.

  14. Stress corrosion crack detection in alloy 600 in high temperature caustic

    Brisson, Bruce W. (Bruce William)
    by Bruce W. Brisson.

  15. Neutronic design of a fission converter-based ephithermal beam for neutron capture theory

    Kiger, William Steadman
    by William Steadman Kiger, III.

  16. A surveillance strategy for four year operating cycle in commercial pressurized water reactors

    Moore, Thomas Joseph
    by Thomas Joseph Moore, Jr.

  17. Set-theoretic control of a pressurized water nuclear power plant

    Chenini, Abdelhamid
    by Abdelhamid Chenini.

  18. Electrochemical study of corrosion phenomena in zirconium alloys

    Treeman, Nicole M
    Shadow corrosion of zirconium alloy fuel cladding in BWR environments, the phenomenon in which accelerated corrosion is experienced when the cladding surface is in close proximity to other metals, has become a potentially life-limiting issue for BWR fuel. Recent results from experimentation at MIT, Halden, and Studvik suggest that a galvanic coupling drives the phenomenon between the cladding and the adjacent material. However, the actual processes involved are not understood. One key parameter that would help in the understanding of the phenomenon would be a measurement of the actual corrosion current between fuel cladding and adjacent materials in the actual...

  19. A fault tolerant architecture for nuclear power plant control systems

    Antonini, Claudio Daniel
    by Claudio Daniel Antonini.

  20. MCNP4B modeling of pebble-bed reactors

    Lebenhaft, Julian R. (Julian Robert), 1954-
    The applicability of the Monte Carlo code MCNP4B to the neutronic modeling of pebblebed reactors was investigated. A modeling methodology was developed based on an analysis of critical experiments carried out at the HTR-PROTIEUS and ASTRA facilities, and the critical loading of the HTR-10 reactor. A body-centred cubic lattice of spheres with a specified packing fraction approximates the pebble bed, and exclusion zones offset the contribution of partial spheres generated by the geometry routines in MCNP4B at the core boundaries. The coated fuel particles are modeled in detail and are distributed over the fuelled region of the fuel sphere using...

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