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Showing 1 to 14 of 14 for “"Research Reactors"”.

  1. Mapping and analyzing nuclear weapons programs development

    An in-depth review of the types of nuclear reactors and their relationship to the development of nuclear weapons was conducted in order to provide a better understanding of the intention of a state in the creation of an internal nuclear program. An analysis of countries that have developed nuclear …

    mit Repository record for Mapping and analyzing nuclear weapons programs development (opens in a new tab)

  2. Characterization of bending fatigue mini-specimens for nuclear materials

    … the economy and performance of current nuclear reactors as well as future nuclear reactors. Measurement of mechanical properties of the material of equipment is required to estimate its safe operating life. Studying fatigue of irradiated specimens is challenging due to space limitation in …

    must-thes Repository record for Characterization of bending fatigue mini-specimens for nuclear materials (opens in a new tab)

  3. Impact assessment for the MIT Research Reactor low enrichment uranium fuel fabrication tolerances

    … of all remaining U.S. high performance research reactors including the MITR. The purpose of this study is to understand the impact of proposed MITR LEU "FYT" fuel element fabrication tolerances on the operation and safety limits of the MITR. Therefore, the effects of fabrication …

    mit Repository record for Impact assessment for the MIT Research Reactor low enrichment uranium fuel fabrication tolerances (opens in a new tab)

  4. Guardians at the Gates of Hell : estimating the risk of nuclear theft and terrorism -- and identifying the highest-priority risks of nuclear theft

    … theft in Russia, Pakistan, and from HEU-fueled research reactors are highlighted. Second, a mathematical model of the global risk of nuclear terrorism is presented, with detailed assessments of what is known about the values of each of the parameters, and of policies that could change each of …

    mit Repository record for Guardians at the Gates of Hell : estimating the risk of nuclear theft and terrorism -- and identifying the highest-priority risks of nuclear theft (opens in a new tab)

  5. The relationship between mechanical properties and microstructure of HT9 steel

    … The structural materials selected for these reactors will need to withstand higher operation temperatures, more neutron irradiation (greater flux), and corrosion from liquid metal coolants. HT9, a ferritic/martensitic alloy, was used in previous fast research reactors (such as EBR-II and …

    uiuc Repository record for The relationship between mechanical properties and microstructure of HT9 steel (opens in a new tab)

  6. Thermal analysis of uranium zirconium hydride fuel using a lead-bismuth gap at LWR operating temperatures

    … being studied for use in advanced light water reactors (LWRs) is uranium zirconium hydride (UZH), a fuel currently being used in the popular TRIGA research reactors. UZH is being considered because unlike the current fuel of choice, uranium dioxide, it is metal based and therefore better able …

    mit Repository record for Thermal analysis of uranium zirconium hydride fuel using a lead-bismuth gap at LWR operating temperatures (opens in a new tab)

  7. Design and optimization of a high thermal flux research reactor via Kriging-based algorithm

    … to increasing demands for the services of research reactors, a 5 MW LEU-fueled research reactor core is developed and optimized to provide high thermal flux within specified limits upon thermal hydraulic performance, cycle length, irradiation utilization, and manufacturability. A novel fuel …

    mit Repository record for Design and optimization of a high thermal flux research reactor via Kriging-based algorithm (opens in a new tab)

  8. Scaling siting criteria and identifying alternative licensing pathways for micro-reactors within the existing regulatory framework

    Micro-reactors are a relatively recent subset of Gen IV reactors currently being developed, and due to their design features (i.e., no refueling onsite, easily transported, and mass produced), micro-reactors have the potential to tap into broader markets never accessed before by the nuclear sector …

    mit Repository record for Scaling siting criteria and identifying alternative licensing pathways for micro-reactors within the existing regulatory framework (opens in a new tab)

  9. Enhanced method for the support of experiment safety analysis

    Submission original under an indefinite embargo labeled 'Open Access'. The submission was exported from vireo on 2024-03-01 without embargo terms

    uiuc Repository record for Enhanced method for the support of experiment safety analysis (opens in a new tab)

  10. Evaluation of the thermal-hydraulic operating limits of the HEU-LEU transition cores for the MIT Research Reactor

    The MIT Research Reactor (MITR) is in the process of conducting a design study to convert from High Enrichment Uranium (HEU) fuel to Low Enrichment Uranium (LEU) fuel. The currently selected LEU fuel design contains 18 plates per element, compared to the existing HEU design of 15 plates per …

    mit Repository record for Evaluation of the thermal-hydraulic operating limits of the HEU-LEU transition cores for the MIT Research Reactor (opens in a new tab)

  11. Experimental study of transient pool boiling heat transfer under exponential power excursion on plate-type heater

    … Reactivity Initiated Accidents (RIAs) in nuclear reactors. The investigation utilized state-of-the-art diagnostics such as Infrared (IR) thermometry and high-speed video (HSV), to gain insight into the physical phenomena and generate a database that could be used for development and validation of …

    mit Repository record for Experimental study of transient pool boiling heat transfer under exponential power excursion on plate-type heater (opens in a new tab)

  12. Graphite as radioactive waste : corrosion behaviour under final repository conditions and thermal treatment

    … from the German AVR and THTR high-temperature reactors is envisaged for direct disposal in a final repository. In this respect, corrosion of the graphite matrix of the spherical fuel elements and pyrocarbon coatings from coated fuel particles is a very important aspect for predicting the …

    aachen Repository record for Graphite as radioactive waste : corrosion behaviour under final repository conditions and thermal treatment (opens in a new tab)

  13. Compact neutron sources for Nuclear Physics: from accelerator-based to laser-driven neutron beams

    … heritage, avionics, and other industrial or research applications. Despite the potential use of neutron beams, the transfer of knowledge outside large research centers is limited by the huge size and complexity of conventional high-intensity neutron sources and the progressive shutdown of …

    sevilla Repository record for Compact neutron sources for Nuclear Physics: from accelerator-based to laser-driven neutron beams (opens in a new tab)

  14. Molecular Dynamics Studies of Grain Boundary Mobilities in Metallic and Oxide Fuels

    … of that energy. In current light water reactors, the most common fuel is uranium dioxide (UO2), an oxide ceramic. There is also ongoing research examining uranium-based based metallic fuels, such as uranium-molybdenum (U-Mo) fuels with low uranium (U) enrichment for research reactors as …

    vt Repository record for Molecular Dynamics Studies of Grain Boundary Mobilities in Metallic and Oxide Fuels (opens in a new tab)