March 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)

    648

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

    468

  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)

    382

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

    286

  5. 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)

    164

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

    163

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

    143

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

    143

  9. 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

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

    132

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

    117

  12. LWR nuclear fuel bundle data for use in fuel bundle handling
    Weihermiller, W.B.; Allison, G.S. (1979)

    116

  13. 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)

    112

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

    102

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

    100

  16. Evaluation of methods for measuring relative permeability of anhydride from the Salado Formation: Sensitivity analysis and data reduction
    Christiansen, R.L.; Kalbus, J.S. [Colorado School of Mines, Golden, CO (United States). Petroleum Engineering Dept.]; Howarth, S.M. [Sandia National Labs., Albuquerque, NM (United States)] (1997)

    98

  17. Study of Caustic Corrosion of Carbon Steel Waste Tanks
    Jenkins, C.F. (1999)

    90

  18. Comparison of CFD Natural Convection and Conduction-only Models for Heat Transfer in the Yucca Mountain Project Drifts
    T. Hadgu; S. Webb; M. Itamura (2004)

    86

  19. Behavior of spent nuclear fuel in water pool storage
    Johnson, A.B. Jr. (1977)

    83

  20. One-dimensional drift-flux model and constitutive equations for relative motion between phases in various two-phase flow regimes
    Ishii, M. (1977)

    82