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  • 1
    Publication Date: 2019-06-27
    Description: A FORTRAN-4 computer program for handling fuel pin data is described. Its main features include standardized output, easy access for data manipulation, and tabulation of important material property data. An additional feature allows simplified preparation of input decks for a fuel swelling computer code (CYGRO-2). Data from over 300 high temperature nitride and carbide based fuel pin irradiations are listed.
    Keywords: NUCLEAR ENGINEERING
    Type: NASA-TM-X-68226 , E-7420
    Format: application/pdf
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  • 2
    Publication Date: 2019-06-27
    Description: Closed-form equations for the lift, drag, and pitching moment coefficients of two dimensional airfoil sections in steady subsonic flow were obtained from published theoretical and experimental results. A turbulent boundary layer was assumed to exist on the airfoil surfaces. The effects of section angle of attack, Mach number, Reynolds number, and the specific airfoil type were considered. The equations were applicable through an angle of attack range of -180 deg to +180 deg; however, above about + or - 20 deg, the section characteristics were assumed to be functions only of angle of attack. A computer program is presented which evaluates the equations for a range of Mach numbers and angles of attack. Calculated results for the NACA 23012 airfoil section were compared with experimental data.
    Keywords: AERODYNAMICS
    Type: NASA-TM-78492 , AVRADCOM-TR-78-15(AM) , A-7464
    Format: application/pdf
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  • 3
    Publication Date: 2019-06-27
    Description: Evaluating in-pile performance of ceramic insulator seals under high neutron and gamma radiation levels
    Keywords: NUCLEAR ENGINEERING
    Type: NASA-TM-X-2180 , E-5683
    Format: application/pdf
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  • 4
    Publication Date: 2019-06-27
    Description: Two groups of six fuel pins each were assembled, encapsulated, and irradiated in the Plum Brook Reactor. The fuel pins employed uranium mononitride (UN) in a tantalum alloy clad. The first group of fuel pins was irradiated for 1500 hours to a maximum burnup of 0.7-atom-percent uranium. The second group of fuel pins was irradiated for about 3000 hours to a maximum burnup of 1.0-atom-percent uranium. The average clad surface temperature during irradiation of both groups of fuel pins was approximately 1200 K. The postirradiation examination revealed the following: no clad failures or fuel swelling occurred; less than 1 percent of the fission gases escaped from the fuel; and the clad of the first group of fuel pins experienced clad embrittlement whereas the second group, which had modified assembly and fabrication procedures to minimize contamination, had a ductile clad after irradiation.
    Keywords: NUCLEAR ENGINEERING
    Type: NASA-TM-X-2732 , E-7192
    Format: application/pdf
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