Neil Emmanuel Todreas - Publications

Affiliations: 
Nuclear engineering Massachusetts Institute of Technology, Cambridge, MA, United States 
Area:
Nuclear engineering
Website:
http://meche.mit.edu/people/faculty/todreas@mit.edu

58 high-probability publications. We are testing a new system for linking publications to authors. You can help! If you notice any inaccuracies, please sign in and mark papers as correct or incorrect matches. If you identify any major omissions or other inaccuracies in the publication list, please let us know.

Year Citation  Score
2018 Zhang Y, Buongiorno J, Golay M, Todreas N. Safety Analysis of a 300-MW(electric) Offshore Floating Nuclear Power Plant in Marine Environment Nuclear Technology. 203: 129-145. DOI: 10.1080/00295450.2018.1433935  0.36
2016 Buongiorno J, Jurewicz J, Golay M, Todreas N. The Offshore Floating Nuclear Plant Concept Nuclear Technology. 194: 1-14. DOI: 10.13182/Nt15-49  0.36
2015 Shirvan K, Ballinger R, Buongiorno J, Forsberg C, Kazimi M, Todreas N. Technology Selection for Offshore Underwater Small Modular Reactors Nuclear Engineering and Technology. DOI: 10.1016/J.Net.2016.06.002  0.36
2009 Todreas N, Hejzlar P, Hassan Y. Flexible conversion fast reactors Nuclear Engineering and Design. 239: 2581. DOI: 10.1016/J.Nucengdes.2009.11.001  0.32
2009 Todreas NE, Hejzlar P, Nikiforova A, Petroski R, Shwageraus E, Fong CJ, Driscoll MJ, Elliott MA, Apostolakis G. Flexible conversion ratio fast reactors: Overview Nuclear Engineering and Design. 239: 2582-2595. DOI: 10.1016/J.Nucengdes.2009.07.014  0.32
2009 Nikiforova A, Hejzlar P, Todreas NE. Lead-cooled flexible conversion ratio fast reactor Nuclear Engineering and Design. 239: 2596-2611. DOI: 10.1016/J.Nucengdes.2009.07.013  0.32
2009 Petroski R, Hejzlar P, Todreas NE. Thermal hydraulic design of a liquid salt-cooled flexible conversion ratio fast reactor Nuclear Engineering and Design. 239: 2612-2625. DOI: 10.1016/J.Nucengdes.2009.07.012  0.32
2009 Fong CJ, Apostolakis GE, Langewisch DR, Hejzlar P, Todreas NE, Driscoll MJ. Reliability analysis of a passive cooling system using a response surface with an application to the flexible conversion ratio reactor Nuclear Engineering and Design. 239: 2660-2671. DOI: 10.1016/J.Nucengdes.2009.07.008  0.32
2009 Hejzlar P, Todreas NE, Shwageraus E, Nikiforova A, Petroski R, Driscoll MJ. Cross-comparison of fast reactor concepts with various coolants Nuclear Engineering and Design. 239: 2672-2691. DOI: 10.1016/J.Nucengdes.2009.07.007  0.32
2009 Malen JA, Todreas NE, Hejzlar P, Ferroni P, Bergles A. Thermal hydraulic design of a hydride-fueled inverted PWR core Nuclear Engineering and Design. 239: 1471-1480. DOI: 10.1016/J.Nucengdes.2009.02.026  0.32
2009 Ganda F, Shuffler C, Greenspan E, Todreas N. Economic analysis of hydride fueled BWR Nuclear Engineering and Design. 239: 1560-1570. DOI: 10.1016/J.Nucengdes.2009.02.024  0.32
2009 Shuffler C, Diller P, Malen J, Todreas N, Greenspan E, Petrovic B. Economic analysis of grid and wire wrap supported hydride and oxide fueled pressurized water reactors Nuclear Engineering and Design. 239: 1505-1530. DOI: 10.1016/J.Nucengdes.2009.01.017  0.32
2009 Diller P, Todreas N, Hejzlar P. Thermal-hydraulic analysis for wire-wrapped PWR cores Nuclear Engineering and Design. 239: 1461-1470. DOI: 10.1016/J.Nucengdes.2009.01.015  0.32
2009 Shuffler C, Trant J, Malen J, Todreas N. Thermal hydraulic analysis for grid supported pressurized water reactor cores Nuclear Engineering and Design. 239: 1442-1460. DOI: 10.1016/J.Nucengdes.2008.12.028  0.32
2009 Greenspan E, Fratoni M, Ganda F, Ginex F, Olander D, Todreas N, Diller P, Ferroni P, Malen J, Romano A, Shuffler C, Trant J, Petrovic B, Garkisch H. Hydride fuel for LWRs-Project overview Nuclear Engineering and Design. 239: 1374-1405. DOI: 10.1016/J.Nucengdes.2008.11.023  0.32
2009 Romano A, Shuffler CA, Garkisch HD, Olander DR, Todreas NE. Fuel performance analysis for PWR cores Nuclear Engineering and Design. 239: 1481-1488. DOI: 10.1016/J.Nucengdes.2008.11.022  0.32
2007 Saccheri JGB, Todreas NE, Driscoll MJ. Design and economic evaluation of an advanced tight-lattice core for the IRIS integral primary system reactor Nuclear Technology. 158: 315-347. DOI: 10.13182/Nt07-A3845  0.32
2006 Romano A, Boscher T, Hejzlar P, Kazimi MS, Todreas NE. Implications of Alternative Strategies for Transition to Sustainable Fuel Cycles Nuclear Science and Engineering. 154: 1-27. DOI: 10.13182/Nse06-A2615  0.96
2004 Dostal V, Hejzlar P, Todreas NE, Buongiorno J. Medium-Power Lead-Alloy Fast Reactor Balance-of-Plant Options Nuclear Technology. 147: 388-405. DOI: 10.13182/Nt147-388  0.44
2004 Hejzlar P, Buongiorno J, MacDonald PE, Todreas NE. Design Strategy and Constraints for Medium-Power Lead-Alloy–Cooled Actinide Burners Nuclear Technology. 147: 321-343. DOI: 10.13182/Nt147-321  0.44
2004 Todreas NE, MacDonald PE, Hejzlar P, Buongiorno J, Loewen EP. Medium-Power Lead-Alloy Reactors: Missions for This Reactor Technology Nuclear Technology. 147: 305-320. DOI: 10.13182/Nt04-A3534  0.44
2004 Romano A, Hejzlar P, Todreas NE. Fertile-Free Fast Lead-Cooled Incinerators for Efficient Actinide Burning Nuclear Technology. 147: 368-387. DOI: 10.13182/Nt04-1  0.44
2004 Carelli MD, Conway LE, Oriani L, Petrović B, Lombardi CV, Ricotti ME, Barroso ACO, Collado JM, Cinotti L, Todreas NE, Grgić D, Moraes MM, Boroughs RD, Ninokata H, Ingersoll DT, et al. The design and safety features of the IRIS reactor Nuclear Engineering and Design. 230: 151-167. DOI: 10.1016/J.Nucengdes.2003.11.022  0.32
2002 Chapin DM, Cohen KP, Davis WK, Kintner EE, Koch LJ, Landis JW, Levenson M, Mandil IH, Pate ZT, Rockwell T, Schriesheim A, Simpson JW, Squire A, Starr C, Stone HE, ... ... Todreas NE, et al. Nuclear safety. Nuclear power plants and their fuel as terrorist targets. Science (New York, N.Y.). 297: 1997-9. PMID 12242425 DOI: 10.1126/Science.1077855  0.32
2002 Romano A, Todreas NE. A Methodology for Selecting High Thermal-Hydraulic Performance Fuel Configurations for Tightly Packed Epithermal Core Designs Nuclear Technology. 139: 61-71. DOI: 10.13182/Nt02-A3304  0.44
2002 Buongiorno J, Todreas NE, Kazimi MS. Heavy-Metal Aerosol Transport in a Lead-Bismuth-Cooled Fast Reactor with In-Vessel Direct-Contact Steam Generation Nuclear Technology. 138: 30-43. DOI: 10.13182/Nt02-A3275  0.96
2002 Carelli M, Miller K, Lombardi C, Todreas N, Greenspan E, Ninokata H, Lopez F, Cinotti L, Collado J, Oriolo F, Alonso G, Moraes M, Boroughs R, Barroso A, Ingersoll D, et al. IRIS: Proceeding towards the preliminary design International Conference On Nuclear Engineering, Proceedings, Icone. 2: 883-888. DOI: 10.1115/ICONE10-22497  0.32
2002 Hejzlar P, Todreas NE, Driscoll MJ, MacDonald PE, Buongiorno J, Weaver KD. Design strategies for lead-alloy-cooled reactors for actinide burning and low-cost electricity production International Conference On Nuclear Engineering, Proceedings, Icone. 2: 771-783. DOI: 10.1115/ICONE10-22377  0.32
2002 Dostal V, Driscoll MJ, Hejzlar P, Todreas NE. A supercritical CO2 gas turbine power cycle for next-generation nuclear reactors International Conference On Nuclear Engineering, Proceedings, Icone. 2: 567-574. DOI: 10.1115/ICONE10-22192  0.32
2002 Davis CB, Kim D, Todreas NE, Kazimi MS. Core power limits for a lead-bismuth natural circulation actinide burner reactor Nuclear Engineering and Design. 213: 165-182. DOI: 10.1016/S0029-5493(02)00049-3  0.32
2000 Gavrilas M, Todreas NE, Driscoll MJ. Design and evaluation of a passively cooled containment for a high-rating pressurized water reactor Nuclear Engineering and Design. 200: 233-249. DOI: 10.1016/S0029-5493(99)00339-8  0.32
2000 Hejzlar P, Todreas NE. Response to Letter to the Editor on the round table discussion on reactor power margins published in Nuclear Engineering and Design 163 (1–2) 1996 Nuclear Engineering and Design. 201: 347-352. DOI: 10.1016/S0029-5493(00)00266-1  0.44
2000 Liu H, Todreas NE, Driscoll MJ. Experimental investigation of a passive cooling unit for nuclear plant containment Nuclear Engineering and Design. 199: 243-255. DOI: 10.1016/S0029-5493(00)00229-6  0.32
2000 Byun CS, Jerng DW, Todreas NE, Driscoll MJ. Conceptual design and analysis of a semi-passive containment cooling system for a large concrete containment Nuclear Engineering and Design. 199: 227-242. DOI: 10.1016/S0029-5493(00)00228-4  0.32
1999 McMahon MV, Driscoll MJ, Pilat EE, Todreas NE. Reload light water reactor core designs for an ultralong operating cycle Nuclear Technology. 126: 32-47. DOI: 10.13182/Nt99-A2956  0.32
1999 Kazimi MS, Todreas NE. Nuclear power economic performance : Challenges and opportunities Annual Review of Energy and the Environment. 24: 139-171. DOI: 10.1146/Annurev.Energy.24.1.139  0.96
1999 Garcia-Delgado L, Driscoll MJ, Meyer JE, Todreas NE. An economically optimum PWR reload core for a 36-month cycle Annals of Nuclear Energy. 26: 659-677. DOI: 10.1016/S0306-4549(98)00086-3  0.32
1998 Gavrilas M, Todreas NE, Driscoll MJ. Containment passive-cooling design concepts Progress in Nuclear Energy. 32: 647-655. DOI: 10.1016/S0149-1970(97)00069-3  0.32
1997 Hejzlar P, Todreas NE, Driscoll MJ. Flooding of a large, passive, pressure-tube light water reactor Nuclear Engineering and Design. 177: 7-24. DOI: 10.1016/S0029-5493(97)00182-9  0.32
1997 Hejzlar P, Mattingly BT, Todreas NE, Driscoll MJ. Advanced fuel elements for passive pressure tube light water reactors Nuclear Engineering and Design. 167: 375-392. DOI: 10.1016/S0029-5493(96)01301-5  0.32
1996 Hejzlar P, Todreas NE, Driscoll MJ. Large passive pressure tube light water reactor with voided calandria Nuclear Technology. 113: 134-144. DOI: 10.13182/Nt96-A35183  0.32
1996 Hejzlar P, Todreas NE, Driscoll MJ. Passive pressure tube light water reactors Nuclear Technology. 113: 123-133. DOI: 10.13182/Nt96-A35182  0.32
1996 Parlatan Y, Todreas NE, Driscoll MJ. Buoyancy and property variation effects in turbulent mixed convection of water in vertical tubes Journal of Heat Transfer. 118: 381-387. DOI: 10.1115/1.2825855  0.32
1996 Gavrilas M, Hejzlar P, Todreas NE, Driscoll MJ. GOTHIC code evaluation of alternative passive containment cooling features Nuclear Engineering and Design. 166: 427-442. DOI: 10.1016/S0029-5493(96)01259-9  0.32
1996 Hejzlar P, Todreas NE. Response of Hejzlar and Todreas to contributors' letters and technical notes Nuclear Engineering and Design. 163: 273-279. DOI: 10.1016/0029-5493(95)01177-3  0.44
1996 Hejzlar P, Todreas NE. Consideration of critical heat flux margin prediction by subcooled or low quality critical heat flux correlations Nuclear Engineering and Design. 163: 215-223. DOI: 10.1016/0029-5493(95)01169-2  0.44
1996 Todreas NE, Hejzlar P. Letter to the editor on the paper by D.C. Groeneveld and L.K.H. Leung, “The 1995 look-up table for critical heat flux in tubes” Nuclear Engineering and Design. 163: 25-26. DOI: 10.1016/0029-5493(95)01155-2  0.44
1995 Hejzlar P, Driscoll MJ, Todreas NE. Physics characteristics of a large, passive, pressure tube light water reactor with voided calandria Nuclear Science and Engineering. 121: 448-460. DOI: 10.13182/Nse95-A24146  0.44
1994 Fu G, Todreas NE, Hejzlar P, Driscoll MJ. Heat transfer correlation for reactor riser in mixed convection air flow Journal of Heat Transfer. 116: 489-492. DOI: 10.1115/1.2911425  0.32
1993 Hejzlar P, Todreas NE, Driscoll MJ. Passive decay heat removal in advanced LWR concepts Nuclear Engineering and Design. 139: 59-81. DOI: 10.1016/0029-5493(93)90262-8  0.32
1992 Barakat ARI, Todreas NE. Mixed convection recirculation flow in a vertical single-rod channel connected to an upper plenum Nuclear Engineering and Design. 132: 317-338. DOI: 10.1016/0029-5493(92)90228-N  0.32
1988 Ro TS, Todreas NE. Energy transfer mechanisms in LMR rod bundles under mixed convection conditions Nuclear Engineering and Design. 108: 343-357. DOI: 10.1016/0029-5493(88)90223-3  0.32
1986 Cheng SK, Todreas NE. Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundles - Bundle friction factors, subchannel friction factors and mixing parameters Nuclear Engineering and Design. 92: 227-251. DOI: 10.1016/0029-5493(86)90249-9  0.32
1984 Schor AL, Kazimi MS, Todreas NE. Advances in two-phase flow modeling for LMFBR applications Nuclear Engineering and Design. 82: 127-155. DOI: 10.1016/0029-5493(84)90208-5  0.96
1982 Gierszewski PJ, Mikic B, Todreas NE. Natural circulation of electrically conducting liquids in fusion reactor blankets Nuclear Engineering and Design. 68: 255-264. DOI: 10.1016/0029-5493(82)90244-8  0.64
1982 Chao J, Gierszewski P, Mikic BB, Todreas NE, McManamy TJ. A performance comparison of lithium, helium, and flibe cooled tube/header fusion blankets Journal of Fusion Energy. 2: 145-159. DOI: 10.1007/Bf01054581  0.48
1979 Chao J, Mikic BB, Todreas NE. Neutronic performance of fusion reactor blankets with different coolants and structural arrangements Nuclear Technology. 45: 113-120. DOI: 10.13182/Nt79-A32302  0.48
1979 Chao J, Mikic BB, Todreas NE. A Parametric Study of a Lithium-Cooled Tokamak Blanket Nuclear Technology. 42: 22-33. DOI: 10.13182/Nt79-A32159  0.48
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