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Showing 1 to 20 of 59 for “"Pressurized Water Reactor"”.

  1. Optimization of hydride fueled pressurized water reactor cores

    … potential benefits of hydride fuel use in light water reactors (LWRs). This pursuit involves implementing an appropriate methodology for design and optimization of hydride and oxide fueled cores. Core design is accomplished for a range of geometries via steady-state and transient thermal …

    mit Repository record for Optimization of hydride fueled pressurized water reactor cores (opens in a new tab)

  2. An inverted hydride-fueled pressurized water reactor concept

    … on pressure drop and fuel temperature apply to reactor types in which, thanks to low operating pressure and/or fuel-coolant chemical compatibility, the inverted core can be designed as to closely resemble a modular repetition of the inverted unit cell, i.e. the so-called continuous inverted …

    mit Repository record for An inverted hydride-fueled pressurized water reactor concept (opens in a new tab)

  3. Transient analysis of hydride fueled pressurized water reactor cores

    … power given specific transient conditions for pressurized water reactors (PWR) loaded with either U02 or UZrH1.6 fuel. Several geometries have been examined with the VIPRE subchannel analysis tool along with MATLAB scripts previously developed to automate VIPRE execution. The transients …

    mit Repository record for Transient analysis of hydride fueled pressurized water reactor cores (opens in a new tab)

  4. Characterization and mitigation of crud at pressurized water reactor conditions

    … Fouling deposits on fuel rods in nuclear reactors, known as crud, can cause a variety of undesirable effects including axial power shifts, accelerated corrosion, increased primary circuit radiation dose, and possible fuel failure. This study revisits the crud problem once again using a …

    mit Repository record for Characterization and mitigation of crud at pressurized water reactor conditions (opens in a new tab)

  5. Analysis of the automatic control of a pressurized water reactor

    Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Electrical Engineering, 1961.

    mit Repository record for Analysis of the automatic control of a pressurized water reactor (opens in a new tab)

  6. Innovative fuel designs for high power density pressurized water reactor

    … energy is to increase the power density of the reactor core. Features of fuel design that enhance the potential for high power density are derived based on characteristics of the pressurized water reactor (PWR) and its related design limits. Those features include: large fuel surface to volume …

    mit Repository record for Innovative fuel designs for high power density pressurized water reactor (opens in a new tab)

  7. An inverted pressurized water reactor design with twisted-tape swirl promoters

    An Inverted Fuel Pressurized Water Reactor (IPWR) concept was previously investigated and developed by Paolo Ferroni at MIT with the effort to improve the power density and capacity of current PWRs by modifying the core geometry. A detailed study was performed to optimize the IPWR design …

    mit Repository record for An inverted pressurized water reactor design with twisted-tape swirl promoters (opens in a new tab)

  8. 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 …

    nps Repository record for Thermal hydraulic performance analysis of a small integral pressurized water reactor core (opens in a new tab)

  9. Alternative passive cooling concepts for a large rating pressurized water reactor containment

    Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1995.

    mit Repository record for Alternative passive cooling concepts for a large rating pressurized water reactor containment (opens in a new tab)

  10. 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 …

    mit Repository record for Thermal hydraulic performance analysis of a small integral pressurized water reactor core (opens in a new tab)

  11. A multiple-loop primary system model for pressurized water reactor plant sensor validation

    Thesis (Ph.D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1984.

    mit Repository record for A multiple-loop primary system model for pressurized water reactor plant sensor validation (opens in a new tab)

  12. Thorium-based mixed oxide fuel in a pressurized water reactor: A feasibility analysis with MCNP

    … thorium-based mixed oxide fuel in a conventional pressurized water reactor for plutonium disposition. Both non-paralyzing and paralyzing dead-time calculations were performed for the Portable Spectroscopic Fast Neutron Probe (N-Probe), which can be used for spent fuel interrogation. Also, a …

    must-thes Repository record for Thorium-based mixed oxide fuel in a pressurized water reactor: A feasibility analysis with MCNP (opens in a new tab)

  13. Investigation of pellet-clad interaction during load-follow operation in a pressurized water reactor using VERA-CS

    … fuel failure risk in a PWR. PWR1, a commercial reactor that performed load-follow power maneuvers in cycle 21, was modeled using VERA-CS. The effects of a jump-in approach, starting depletion in cycle 17 as compared to cycle 1, were shown to be negligible after two cycles of depletion. Both low …

    uiuc Repository record for Investigation of pellet-clad interaction during load-follow operation in a pressurized water reactor using VERA-CS (opens in a new tab)

  14. EXPERIMENTAL STUDIES OF THE CHEMICAL EFFECTS OF ZINC-BEARING MATERIALS FOLLOWING A LOSS-OF-COOLANT ACCIDENT IN A PRESSURIZED WATER REACTOR

    … NRC) to assess the effect of debris loading on pressurized water reactor (PWR) emergency core cooling systems (ECCS) sump strainers during a Loss-of-Coolant Accident (LOCA). Potential contributors to the debris loading include latent dirt, fiberglass insulation, paints, epoxies, and chemical …

    unm Repository record for EXPERIMENTAL STUDIES OF THE CHEMICAL EFFECTS OF ZINC-BEARING MATERIALS FOLLOWING A LOSS-OF-COOLANT ACCIDENT IN A PRESSURIZED WATER REACTOR (opens in a new tab)

  15. Hardware-in-the-loop simulation of pressurized water reactor steam-generator water-level control, designed for use within physically distributed testing environments

    … digital sensing and control of steam generator water-level. The model was created with an intention to serve as a component within a larger, distributed digital systems conceptual testing facility. In the present application, a software model simulates a nuclear pressurized water reactor core, …

    ohiolink Repository record for Hardware-in-the-loop simulation of pressurized water reactor steam-generator water-level control, designed for use within physically distributed testing environments (opens in a new tab)

  16. Determining the moderator temperature coefficient in a PWR by stochastic fluctuation analysis

    … the moderator temperature coefficient (MTC) in a pressurized water reactor is described and compared to an analytical model. The method correlates fluctuations in the neutron flux with fluctuations in the coolant temperature. Results show that the frequency response function between the in-core …

    vt Repository record for Determining the moderator temperature coefficient in a PWR by stochastic fluctuation analysis (opens in a new tab)

  17. Application of advanced fuel concepts for use in innovative pressurized water reactors

    … alternative fuel and cladding combinations in a pressurized water reactor (PWR) environment. In the switch from a UO2 with zirconium-based cladding to any other combination, there is a multitude of questions that need to be answered. This work examines three of these knowledge gaps: (1) the …

    mit Repository record for Application of advanced fuel concepts for use in innovative pressurized water reactors (opens in a new tab)

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