Romney B. Duffey

Articles in Scholarly Journals [Incomplete List]

  1. Climate change gains more from nuclear substitution than from conservation
    Nuclear Engineering and Design, vol. 236, no. 14-16, pp. 1657–1667, 2006
  2. Sustainable futures using nuclear energy
    Progress in Nuclear Energy, vol. 47, no. 1-4, pp. 535–543, 2005
  3. Predicting tragedies, accidents, errors and failures using a learning environment
    Science and Technology of Advanced Materials, vol. 6, no. 8, pp. 878–882, 2005
  4. The computable dimension of trees of infinite height
    Journal of Symbolic Logic, vol. 70, no. 1, pp. 111–141, 2005
  5. Sustainable and economic hydrogen cogeneration from nuclear energy in competitive power markets
    Energy, vol. 30, no. 14, pp. 2690–2702, 2005
  6. Experimental heat transfer of supercritical carbon dioxide flowing inside channels (survey)
    Nuclear Engineering and Design, vol. 235, no. 8, pp. 913–924, 2005
  7. Experimental heat transfer in supercritical water flowing inside channels (survey)
    Nuclear Engineering and Design, vol. 235, no. 22, pp. 2407–2430, 2005
  8. Heat transfer to supercritical fluids flowing in channels—empirical correlations (survey)
    Nuclear Engineering and Design, vol. 230, no. 1-3, pp. 69–91, 2004
  9. Hydraulic resistance of fluids flowing in channels at supercritical pressures (survey)
    Nuclear Engineering and Design, vol. 231, no. 2, pp. 187–197, 2004
  10. Innovation in technology for the least product price and cost ? a new minimum cost relation for reductions during technological learning
    International Journal of Energy Technology and Policy, vol. 2, no. 1/2, p. 106, 2004
  11. Errors in technological systems
    Human Factors and Ergonomics in Manufacturing, vol. 13, no. 4, pp. 279–291, 2003
  12. Natural-convection studies for advanced CANDU reactor concepts
    Nuclear Engineering and Design, vol. 215, no. 1-2, pp. 27–38, 2002
  13. Stability, DNB, and CHF in natural circulation two-phase flow
    International Communications in Heat and Mass Transfer, vol. 25, no. 2, pp. 161–174, 1998
  14. TPG response to the foregoing letters-to-the-editor
    Nuclear Engineering and Design, vol. 132, no. 3, pp. 431–436, 1992
  15. Stabilite de l'assechement et apparition aux faibles debitsStabilität und einsetzen des “dryout” bei kleinen massenstromdichten?c?o????oc?? ? Ha?a?o ?p???ca ?e??oo?MeHa ?p? H????? c?opoc??? ?e?eH?? ??eH??
    International Journal of Heat and Mass Transfer, vol. 34, no. 2, pp. 473–481, 1991
  16. Quantifying reactor safety margins part 1: An overview of the code scaling, applicability, and uncertainty evaluation methodology
    Nuclear Engineering and Design, vol. 119, no. 1, pp. 1–15, 1990
  17. Quantifying reactor safety margins part 3: Assessment and ranging of parameters
    Nuclear Engineering and Design, vol. 119, no. 1, pp. 33–65, 1990
  18. Quantifying reactor safety margins Part 5: Evaluation of scale-up capabilities of best estimate codes
    Nuclear Engineering and Design, vol. 119, no. 1, pp. 97–107, 1990
  19. Quantifying reactor safety margins Part 6: A physically based method of estimating pwr large break loss of coolant accident pct
    Nuclear Engineering and Design, vol. 119, no. 1, pp. 109–117, 1990
  20. Natural circulation phenomena relevant to small breaks and transients
    Nuclear Engineering and Design, vol. 102, no. 2, pp. 115–128, 1987
  21. Piping response testing associated with pipe rupture
    Nuclear Engineering and Design, vol. 89, no. 2-3, pp. 477–491, 1985
  22. The prediction of two-phase mixture level and hydrodynamically-controlled dryout under low flow conditions
    International Journal of Multiphase Flow, vol. 7, no. 5, pp. 521–543, 1981
  23. Acoustic wave propagation in a flowing liquid-vapour mixture
    International Journal of Multiphase Flow, vol. 4, no. 3, pp. 303–322, 1978
  24. The effects of countercurrent single and two-phase flows on the quenching rate of hot surfaces
    International Journal of Multiphase Flow, vol. 4, no. 2, pp. 117–140, 1978
  25. The effect of thermal diffusion from fuel pellets on rewetting of overheated water reactor pins
    Nuclear Engineering and Design, vol. 41, no. 2, pp. 165–173, 1977
  26. Wetting delay due to film and transition boiling on hot surfaces
    Nuclear Engineering and Design, vol. 36, no. 2, pp. 169–181, 1976
  27. A study of the unsteady flow and heat transfer in the reflooding of water reactor cores
    Annals of Nuclear Energy, vol. 3, no. 4, pp. 197–210, 1976
  28. The quenching of irradiated fuel pins
    Nuclear Engineering and Design, vol. 32, no. 2, pp. 182–190, 1975
  29. The physics of rewetting in water reactor emergency core cooling
    Nuclear Engineering and Design, vol. 25, no. 3, pp. 379–394, 1973
  30. Measurements of transient heat fluxes and vapour generation rates in water
    International Journal of Heat and Mass Transfer, vol. 16, no. 8, pp. 1513–1514, 1973
  31. Transient and forced convective film boiling in subcooled water at low reynolds numbers
    International Journal of Heat and Mass Transfer, vol. 16, no. 8, pp. 1652–1654, 1973
  32. Étude expérimentale des processus de transfert d'energie au cours d'explosions thermiques
    International Journal of Heat and Mass Transfer, vol. 14, no. 10, pp. 1631–1634, 1971
  33. Observations of high-frequency micropulsations at a moderate latitude
    Journal of Atmospheric and Terrestrial Physics, vol. 32, no. 8, pp. 1365–1372, 1970