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Showing 1 to 7 of 7 for “"thermal-hydraulic design"”.

  1. Thermal Hydraulic Design of a Temperature Controlled Materials Irradiation Facility

    Made available in DSpace on 2017-07-06T18:55:13Z (GMT). No. of bitstreams: 3 Malone_George_J_MS.pdf: 39166083 bytes, checksum: a903041edb195813700e77f06eb49ceb (MD5) Malone_George_J_MS_ABS.pdf: 529193 bytes, checksum: 1783a6db3c70fc68a04c3b838ba95ef4 (MD5) license.txt: 4813 bytes, checksum: …

    uiuc Repository record for Thermal Hydraulic Design of a Temperature Controlled Materials Irradiation Facility (opens in a new tab)

  2. Thermal hydraulic design of a salt-cooled highly efficient environmentally friendly reactor

    A 1 OOOMWth liquid-salt cooled thermal spectrum reactor was designed with a long fuel cycle, and high core exit temperature. These features are desirable in a reactor designed to provide process heat applications such as oil refinery needs of heat and electricity. The reactor uses the binary salt …

    mit Repository record for Thermal hydraulic design of a salt-cooled highly efficient environmentally friendly reactor (opens in a new tab)

  3. Thermal hydraulic design of a 2400 MW t̳h̳ direct supercritical CO₂-cooled fast reactor

    … alternative to the mainstream helium cooled GFR design. A steady state core design was developed which utilizes an innovative, high fuel volume fraction, vented Tube-In-Duct (TID) fuel assembly. Through an extensive series of iterative calculations, RELAP5-3D was then used to evaluate the natural …

    mit Repository record for Thermal hydraulic design of a 2400 MW t̳h̳ direct supercritical CO₂-cooled fast reactor (opens in a new tab)

  4. Thermal hydraulic design and analysis of a large lead-cooled reactor with flexible conversion ratio

    … goal of this project is to develop conceptual designs of fast flexible conversion ratio reactors using lead and liquid salt coolants and compare the results with the gas cooled fast reactor developed in an MIT NERI project and the sodium cooled reactor under development at ANL. This thesis is …

    mit Repository record for Thermal hydraulic design and analysis of a large lead-cooled reactor with flexible conversion ratio (opens in a new tab)

  5. Optimization of hydride fueled pressurized water reactor cores

    … 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 hydraulic analyses, which yield the maximum power, and fuel performance and neutronics studies, …

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

  6. Two-phase CFD analyses in fuel assembly sub-channels of Pressurized Water Reactors under swirl conditions

    … widely applied in nuclear industry for the thermal-hydraulic design optimization of fuel assemblies (FA). In contrast, two-phase CFD-applications are still in the state of development. The work presented in this thesis shows contributions towards the detailed two-phase modeling of boiling …

    qucosa-diss

  7. Design Space Exploration for Salt Cooled Reactor Systems

    … an AGR-like FHR concept. It explored the thermal-hydraulic and neutronic design space of a number of AGR-like FHR assembly options covering combinations of three fuel geometries: 1) solid pin, 2) annular pin and 3) plate type fuel; three coolant options: 1) FLiBe 2) FLiNaK and 3) NaF-ZrF4, …

    cambridge Repository record for Design Space Exploration for Salt Cooled Reactor Systems (opens in a new tab)