Consideration of critical heat flux margin prediction by subcooled or low quality critical heat flux correlations : Round table discussion on reactor power marginsHEJZLAR, P; TODREAS, N. E.Nuclear engineering and design. 1996, Vol 163, Num 1-2, pp 215-224, issn 0029-5493, 9 p.Article

An experimental investigation of a passive cooling unit for nuclear plant containmentLIU, H; TODREAS, N. E; DRISCOLL, M. J et al.Nuclear engineering and design. 2000, Vol 199, Num 3, pp 243-255, issn 0029-5493Article

Buoyancy and property variation effects in turbulent mixed convection of water in vertical tubesPARLATAN, Y; TODREAS, N. E; DRISCOLL, M. J et al.Journal of heat transfer. 1996, Vol 118, Num 2, pp 381-387, issn 0022-1481Article

Effective thermal conductivity and edge conductance model for a spent-fuel assemblyMANTEUFEL, R. D; TODREAS, N. E.Nuclear technology. 1994, Vol 105, Num 3, pp 421-440, issn 0029-5450Article

Mixed convection recirculation flow in a vertical single-rod channel connected to an upper plenumBARAKAT, A.-R. I; TODREAS, N. E.Nuclear engineering and design. 1992, Vol 132, Num 3, pp 317-338, issn 0029-5493Article

Heavy-metal aerosol transport in a lead-bismuth-cooled fast reactor with in-vessel direct-contact steam generationBUONGIORNO, J; TODREAS, N. E; KAZIMI, M. S et al.Nuclear technology. 2002, Vol 138, Num 1, pp 30-43, issn 0029-5450Article

Large passive pressure tube light water reactor with voided calandriaHEJZLAR, P; TODREAS, N. E; DRISCOLL, M. J et al.Nuclear technology. 1996, Vol 113, Num 2, pp 134-144, issn 0029-5450Article

Analytic formulae for the effective conductivity of a square or hexagonal array of parallel tubesMANTEUFEL, R. D; TODREAS, N. E.International journal of heat and mass transfer. 1994, Vol 37, Num 4, pp 647-657, issn 0017-9310Article

Physics characteristics of a large, passive, pressure tube light water reactor with voided calandriaHEJZLAR, P; DRISCOLL, M. J; TODREAS, N. E et al.Nuclear science and engineering. 1995, Vol 121, Num 3, pp 448-460, issn 0029-5639Article

Mixed convection friction factors and Nusselt numbers in vertical annular and subchannel geometriesIANNELLO, V; SUH, K. Y; TODREAS, N. E et al.International journal of heat and mass transfer. 1988, Vol 31, Num 10, pp 2175-2189, issn 0017-9310Article

Conceptual design features for a passive light water cooled and moderated pressure tube reactor (PLPTR)JAN RU TANG; TODREAS, N. E; DRISCOLL, M. J et al.Nuclear technology. 1994, Vol 107, Num 1, pp 49-62, issn 0029-5450Conference Paper

Criteria for the onset of flow recirculation and onset of mixed convection in vertical rod bundlesSYMOLON, P. D; TODREAS, N. E; ROHSENOW, W. M et al.Journal of heat transfer. 1987, Vol 109, Num 1, pp 138-145, issn 0022-1481Article

Design and economic evaluation of an advanced tight-lattice core for the iris integral primary system reactorSACCHERI, J. G. B; TODREAS, N. E; DRISCOLL, M. J et al.Nuclear technology. 2007, Vol 158, Num 3, pp 315-347, issn 0029-5450, 33 p.Article

Steady state thermal-hydraulic analysis of hydride-fueled grid-supported BWRsFERRONI, P; HANDWERK, C. S; TODREAS, N. E et al.Nuclear engineering and design. 2009, Vol 239, Num 8, pp 1544-1559, issn 0029-5493, 16 p.Article

Advanced fuel elements for passive pressure tube light water reactorsHEJZLAR, P; MATTINGLY, B. T; TODREAS, N. E et al.Nuclear engineering and design. 1997, Vol 167, Num 3, pp 375-392, issn 0029-5493Article

The design and safety features of the IRIS reactorCARELLI, Mario D; CONWAY, L. E; GRGIC, D et al.Nuclear engineering and design. 2004, Vol 230, Num 1-3, pp 151-167, issn 0029-5493, 17 p.Conference Paper

GOTHIC code evaluation of alternative passive containment cooling featuresGAVRILAS, M; HEJZLAR, P; TODREAS, N. E et al.Nuclear engineering and design. 1996, Vol 166, Num 3, pp 427-442, issn 0029-5493Conference Paper

The design and evaluation of a passively cooled containment for a high-rating pressurized water reactorGAVRILAS, M; TODREAS, N. E; DRISCOLL, M. J et al.Nuclear engineering and design. 2000, Vol 200, Num 1-2, pp 233-249, issn 0029-5493Conference Paper

Reload light water reactor core designs for an ultralong operating cycleMCMAHON, M. V; DRISCOLL, M. J; PILAT, E. E et al.Nuclear technology. 1999, Vol 126, Num 1, pp 32-47, issn 0029-5450Article

Flooding of a large, passive, pressure-tube light water reactorHEJZLAR, P; TODREAS, N. E; DRISCOLL, M. J et al.Nuclear engineering and design. 1997, Vol 177, Num 1-3, pp 7-24, issn 0029-5493Conference Paper