December 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)

    293

  2. Concepts of Model Verification and Validation
    B.H.Thacker; S.W.Doebling; F.M.Hemez; M.C. Anderson; J.E. Pepin; E.A. Rodriguez (2004)

    229

  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)

    217

  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)

    155

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

    144

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

    116

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

    116

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

    102

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

    102

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

    102

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

    91

  12. 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)

    70

  13. 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)

    68

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

    62

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

    56

  16. Ultrasonic methods for measuring liquid viscosity and volume percent of solids
    Sheen, S.H.; Chien, H.T.; Raptis, A.C. (1997)

    55

  17. Large-scale breeder reactor prototype mechanical pump conceptual design study, hot leg
    Not Available (1976)

    53

  18. Aging of nuclear station diesel generators: Evaluation of operating and expert experience: Phase 1, Study
    Hoopingarner, K.R.; Vause, J.W.; Dingee, D.A.; Nesbitt, J.F. (1987)

    50

  19. 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)

    47

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

    47

Last updated on Tuesday 17 January 2017