June 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)

    305

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

    296

  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)

    245

  4. Cleaning Contaminated Water at Fukushima
    Rende, Dean; Nenoff, Tina (2013)

    204

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

    146

  6. 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)

    104

  7. LONG-TERM DYNAMICS OF RADIONUCLIDE VERTICAL MIGRATION IN SOILS OF THE CHERNOBYL NUCLEAR POWER PLANT EXCLUSION ZONE
    Farfan, E (2009)

    100

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

    97

  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)

    87

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

    83

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

    80

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

    72

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

    70

  14. Materials and design bases issues in ASME Code Case N-47
    Huddleston, R.L.; Swindeman, R.W. (Oak Ridge National Lab., TN (United States)) (1993)

    64

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

    62

  16. Source term estimation during incident response to severe nuclear power plant accidents
    McKenna, T.J.; Glitter, J.G. (1988)

    54

  17. 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)

    53

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

    52

  19. Synthesis, structural characterization, and performance evaluation of resorcinol-formaldehyde (R-F) ion-exchange resin
    Hubler, T.L.; Franz, J.A.; Shaw, W.J.; Bryan, S.A.; Hallen, R.T.; Brown, G.N.; Bray, L.A.; Linehan, J.C. (1995)

    43

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

    43

Last updated on Tuesday 14 June 2016