December 2015 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)

    432

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

    323

  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)

    250

  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)

    223

  5. Minimum Velocity Required to Transport Solid Particles from the 2H-Evaporator to the Tank Farm
    Poirier, M.R. (2000)

    187

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

    131

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

    114

  8. 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)

    108

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

    90

  10. Flow-induced vibration of circular cylindrical structures
    Chen, S.S. (1985)

    90

  11. 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)

    87

  12. 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)

    86

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

    82

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

    76

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

    75

  16. 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)

    73

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

    71

  18. 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)

    60

  19. Criticality calculations with MCNP{sup TM}: A primer
    Mendius, P.W. [ed.]; Harmon, C.D. II; Busch, R.D.; Briesmeister, J.F.; Forster, R.A. (1994)

    60

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

    58

Last updated on Tuesday 14 June 2016