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Showing 1 to 20 of 434 for “"Coolant"”.

  1. Thermal Properties of Candidate Coolant Salts

    … seeks to investigate a collection of promising coolant salts in depth with acknowledgment to those past studies. LiF-NaF-KF (46.5-11.5-42.0 mol%) will be used as a calibration standard and for the purpose of verifying our methodology. Specifically, FLiNaK was used in the development of …

    vt Repository record for Thermal Properties of Candidate Coolant Salts (opens in a new tab)

  2. Chemical characterization of simulated boiling water reactor coolant

    Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1990, and Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Chemical Engineering, 1990.

    mit Repository record for Chemical characterization of simulated boiling water reactor coolant (opens in a new tab)

  3. Experimental Investigation of Turbulent Pipe Flow With Coolant Injection

    Made available in DSpace on 2014-12-04T23:10:54Z (GMT). No. of bitstreams: 1 0018347.pdf: 3653959 bytes, checksum: 82de799bcfc4987e44a242157b20419a (MD5) Previous issue date: 1956

    uiuc Repository record for Experimental Investigation of Turbulent Pipe Flow With Coolant Injection (opens in a new tab)

  4. Modeling of corrosion product transport in PWR primary coolant

    Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1990.

    mit Repository record for Modeling of corrosion product transport in PWR primary coolant (opens in a new tab)

  5. Decontamination studies of simulated PWR primary coolant system components

    Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1990.

    mit Repository record for Decontamination studies of simulated PWR primary coolant system components (opens in a new tab)

  6. Computer model of a nuclear reactor primary coolant pump

    Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1982.

    mit Repository record for Computer model of a nuclear reactor primary coolant pump (opens in a new tab)

  7. Nerva-derived reactor coolant channel model for Mars mission applications

    NERVA-Derived Reactor Coolant Channel Model for Mars Mission Applications presents the results of a computational fluid dynamics (CFD) study of a 1.3m NERVA-Derived Reactor (NDR) coolant channel; The CFD code FLOW-3D was used to model the flow of gaseous hydrogen through the core of a NDR. Hydrogen …

    unlv Repository record for Nerva-derived reactor coolant channel model for Mars mission applications (opens in a new tab)

  8. BWR coolant chemistry studies using a recirculating in-pile loop

    Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1995.

    mit Repository record for BWR coolant chemistry studies using a recirculating in-pile loop (opens in a new tab)

  9. Heat transfer and fluid flow aspects of fuel-coolant interactions.

    Thesis. 1979. Ph.D. cn--Massachusetts Institute of Technology. Dept. of Nuclear Engineering.

    mit Repository record for Heat transfer and fluid flow aspects of fuel-coolant interactions. (opens in a new tab)

  10. Coolant distribution control in satellite structural panels using electrohydrodynamic conduction pumping

    … conduction pumping is well suited for pumping coolants in space-borne thermal control systems. Advantages of EHD pumps include light-weight, simple designs, no moving parts, fast response times, and low power consumption. The EHD conduction pumping phenomenon is a result of electrical …

    unm Repository record for Coolant distribution control in satellite structural panels using electrohydrodynamic conduction pumping (opens in a new tab)

  11. Theoretical studies on some aspects of molten fuel-coolant thermal interaction.

    Massachusetts Institute of Technology. Dept. of Nuclear Engineering. Thesis. 1973. Ph.D.

    mit Repository record for Theoretical studies on some aspects of molten fuel-coolant thermal interaction. (opens in a new tab)

  12. Improved Efficiency in Nuclear Power Plants via Binary Mixture Coolant Kalina Cycle

    Made available in DSpace on 2017-07-06T18:56:04Z (GMT). No. of bitstreams: 3 Romatoski_Rebecca_R_MS.pdf: 4325871 bytes, checksum: cc710dd69826b71e6ffac1fdbb383282 (MD5) Romatoski_Rebecca_R_MS_ABS.pdf: 11053 bytes, checksum: e291aa0c2f8ccf5eb2dd3263d08c7e34 (MD5) license.txt: 4813 bytes, checksum: …

    uiuc Repository record for Improved Efficiency in Nuclear Power Plants via Binary Mixture Coolant Kalina Cycle (opens in a new tab)

  13. Design, construction and commissioning of an in-pile BWR coolant chemistry loop

    Thesis (Sc. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1991.

    mit Repository record for Design, construction and commissioning of an in-pile BWR coolant chemistry loop (opens in a new tab)

  14. A passively-safe fusion reactor blanket with helium coolant and steel structure

    Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1994.

    mit Repository record for A passively-safe fusion reactor blanket with helium coolant and steel structure (opens in a new tab)

  15. Investigations in coolant mixing and flow split for LMFBR wire wrapped assemblies.

    Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Engineering, 1978

    mit Repository record for Investigations in coolant mixing and flow split for LMFBR wire wrapped assemblies. (opens in a new tab)

  16. Rayleigh Flow of Two-Phase Nitrous Oxide as a Hybrid Rocket Nozzle Coolant

    … hybrid rocket’s converging-diverging nozzle as a coolant. While this coolant system has proven effective empirically in previous tests, the physics behind the flow of the two-phase mixture is largely unexplained. This thesis provides a method for predicting some of its behavior by modeling it …

    calpoly Repository record for Rayleigh Flow of Two-Phase Nitrous Oxide as a Hybrid Rocket Nozzle Coolant (opens in a new tab)

  17. Evaluation of multilayer silicon carbide composite cladding under loss of coolant accident conditions

    … all of which are important during a loss of coolant accident (LOCA). To improve the performance of SiC cladding, a multilayered architecture consisting of layers of monolithic SiC (mSiC) and SiC/SiC ceramic matrix composite (CMC) has been proposed. In this work, the mechanical performance of …

    mit Repository record for Evaluation of multilayer silicon carbide composite cladding under loss of coolant accident conditions (opens in a new tab)

  18. Effects of Nodalization on Containment Analysis in a Loss of Coolant Accident Using GOTHIC

    Existing containment models for a loss of coolant accident at many nuclear power plants were created in the 1970s using older computer technology and thermal hydraulic models which were available at that time. While conservative, these models may not present the detail necessary to identify …

    vt Repository record for Effects of Nodalization on Containment Analysis in a Loss of Coolant Accident Using GOTHIC (opens in a new tab)

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