June 2016 Most Viewed Documents for Fission And Nuclear Technologies

  1. Estimation of gas leak rates through very small orifices and channels. [From sealed PuO/sub 2/ containers under accident conditions]
    Bomelburg, H.J. (1977)

    449

  2. Forces in bolted joints: analysis methods and test results utilized for nuclear core applications (LWBR Development Program)
    Crescimanno, P.J.; Keller, K.L. (1981)

    280

  3. Stress analysis and evaluation of a rectangular pressure vessel. [For equipment for sampling Hanford tank radwaste]
    Rezvani, M.A.; Ziada, H.H. (Westinghouse Hanford Co., Richland, WA (United States)); Shurrab, M.S. (Westinghouse Savannah River Co., Aiken, SC (United States)) (1992)

    279

  4. System Definition and Analysis: Power Plant Design and Layout
    NONE (1996)

    252

  5. Nuclear magnetic resonance measurement of ammonia diffusion in dense solid-liquid slurries. Revision 1
    Bobroff, S.; Phillips, R.J. [Univ. of California, Davis, CA (United States). Dept. of Chemical Engineering]; Shekarriz, A. [Pacific Northwest National Lab., Richland, WA (United States)] (1998)

    141

  6. Evaluation of Modal Combination Methods for Seismic Response Spectrum Analysis
    Chokshi, N.; Kenneally, R.; Morante, R.; Norris, W.; Wang, Y. (1999)

    135

  7. Graphite design handbook
    Ho, F.H. (1988)

    120

  8. Porosity, permeability, and their relationship in granite, basalt, and tuff
    Not Available (1983)

    116

  9. LABORATORY STUDY FOR THE REDUCTION OF CHROME (VI) TO CHROME (III) USING SODIUM METABISULFITE UNDER ACIDIC CONDITIONS
    DUNCAM JB; GUTHRIE MD; LUECK KJ; AVILA M (2007)

    109

  10. Feed-pump hydraulic performance and design improvement, Phase I: research program design. Final report
    Brown, W.H.; Gopalakrishnan, S.; Fehlau, R.; Thompson, W.E.; Wilson, D.G. (1982)

    107

  11. Thermophysical properties of sodium nitrate and sodium chloride solutions and their effects on fluid flow in unsaturated media
    Xu, Tianfu; Pruess, Karsten (2001)

    105

  12. Interim glycol flowsheet reduction/oxidation (redox) model for the Defense Waste Processing Facility (DWPF)
    Jantzen, C. M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)]; Williams, M. S. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)]; Zamecnik, J. R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)]; Missimer, D. M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)] (2016)

    89

  13. Wall thinning acceptance criteria for degraded carbon steel piping systems using FAD methodology
    Lam, P.S.; Gupta, N.K. (1995)

    85

  14. Active Well Counting Using New PSD Plastic Detectors
    Hausladen, Paul [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)]; Newby, Jason [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)]; McElroy, Robert Dennis [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)] (2015)

    82

  15. Electrochemical oxidation of 243Am(III) in nitric acid by a terpyridyl-derivatized electrode
    Dares, C. J.; Lapides, A. M.; Mincher, B. J.; Meyer, T. J. (2015)

    77

  16. Erosion/corrosion-induced pipe wall thinning in US Nuclear Power Plants
    Wu, P.C. (1989)

    77

  17. Handbook of human-reliability analysis with emphasis on nuclear power plant applications. Final report
    Swain, A D; Guttmann, H E (1983)

    73

  18. Impact of scaling on the nitric-glycolic acid flowsheet
    Lambert, D. [Savannah River Site (SRS), Aiken, SC (United States)] (2016)

    72

  19. Effect of Hurricane Andrew on the Turkey Point Nuclear Generating Station from August 20--30, 1992. [Final report]
    Hebdon, F.J. [Institute of Nuclear Power Operations, Atlanta, GA (United States)] (1993)

    71

  20. Vapor-liquid equilibria for nitric acid-water and plutonium nitrate-nitric acid-water solutions
    Maimoni, A. (1980)

    70

Last updated on Thursday 07 July 2016