Michael J. Driscoll - Publications

Affiliations: 
Nuclear Science and Engineering Massachusetts Institute of Technology, Cambridge, MA, United States 
Area:
Nuclear Engineering
Website:
https://mitei.mit.edu/research/energy-faculty/michael-j-driscoll

121 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
2014 Fei T, Driscoll MJ, Shwageraus E. Uranium startup fast reactors with metal fuel using once-through fuel cycle Nuclear Technology. 186: 378-389. DOI: 10.13182/Nt13-21  1
2014 Bates EA, Salazar A, Driscoll MJ, Baglietto E, Buongiorno J. Plug design for deep borehole disposal of high-level nuclear waste Nuclear Technology. 188: 280-291. DOI: 10.13182/Nt12-166  1
2014 Bates EA, Buongiorno J, Baglietto E, Driscoll MJ. Mechanical stresses affecting deep borehole disposal of high level nuclear waste International Conference On Nuclear Engineering, Proceedings, Icone. 4. DOI: 10.1115/ICONE22-31259  1
2014 Bates EA, Driscoll MJ, Lester RK, Arnold BW. Can deep boreholes solve America's nuclear waste problem? Energy Policy. 72: 186-189. DOI: 10.1016/J.Enpol.2014.03.003  1
2013 Driscoll MJ, Stübner R, Ebrahimi T, Foulonneau M, Nürnberger A, Scharnhorst A, Springer J. COST actions and digital libraries: Between sustaining best practices and unleashing further potential Lecture Notes in Computer Science (Including Subseries Lecture Notes in Artificial Intelligence and Lecture Notes in Bioinformatics). 8092: 478-479. DOI: 10.1007/978-3-642-40501-3_65  0.01
2013 Bates EA, Baglietto E, Driscoll MJ, Buongiorno J. Onset and stability of natural convection in deep boreholes 14th International High-Level Radioactive Waste Management Conference, Ihlrwmc 2013: Integrating Storage, Transportation, and Disposal. 2: 762-768.  1
2013 Lubchenko N, Baglietto E, Driscoll MJ. Towards the development and application of borehole virtual reality simulation tools Transactions of the American Nuclear Society. 109: 367-369.  1
2012 Driscoll MJ, Lester RK, Jensen KG, Arnold BW, Swift PN, Brady PV. Technology and policy aspects of deep borehole nuclear waste disposal Nuclear Technology. 180: 111-121. DOI: 10.13182/Nt12-A14523  1
2012 Bates EA, Buongiorno J, Baglietto E, Driscoll MJ. Transient thermal modeling of a deep borehole repository Transactions of the American Nuclear Society. 106: 254-257.  1
2012 Salazar A, Bates EA, Driscoll MJ. Plugging of deep boreholes used for HLW disposal Transactions of the American Nuclear Society. 107: 293-294.  1
2012 Richard JG, Fei T, Driscoll MJ. The innovations in fuel cycle research awards program - A student competition recycling SFR uranium startup fuel Transactions of the American Nuclear Society. 107: 136-139.  1
2012 Forsberg CW, Lee Y, Kulhanek M, Driscoll MJ. Gigawatt-year nuclear-geothermal energy storage for light-water and high-temperature reactors International Congress On Advances in Nuclear Power Plants 2012, Icapp 2012. 4: 2728-2737.  1
2012 Vitillo F, Todreas NE, Driscoll MJ. A vented inverted fuel assembly design for an SFR International Congress On Advances in Nuclear Power Plants 2012, Icapp 2012. 1: 648-657.  1
2012 Fei T, Richard JG, Kersting AR, Don SM, Oi C, Driscoll MJ, Shwageraus E. A survey of alternative once-through fast reactor core designs International Congress On Advances in Nuclear Power Plants 2012, Icapp 2012. 3: 1562-1571.  1
2012 Driscoll MJ, Jensen KG. Policy issues associated with deep-borehole HLW disposal Radwaste Solutions. 19: 42-45.  1
2012 Denman M, Todreas N, Driscoll M. Review of fuel/cladding eutectic formation in metallic SFR fuel pins International Congress On Advances in Nuclear Power Plants 2012, Icapp 2012. 1: 667-676.  1
2011 Lee Y, Forsberg CW, Driscoll MJ. Conceptual design of nuclear-geothermal energy storage systems for variable electricity production Transactions of the American Nuclear Society. 105: 671-672.  1
2011 Fei T, Shwageraus E, Driscoll MJ. A cost-effective U-235 once-through startup mode for SFRs Transactions of the American Nuclear Society. 104: 734-735.  1
2011 Dozier FE, Driscoll MJ, Buongiorno J. Host rock temperature around a borehole containing HLW Transactions of the American Nuclear Society. 105: 229-231.  1
2011 Bates EA, Driscoll MJ, Buongiorno J. Drop-in concept for deep borehole canister emplacement 13th International High-Level Radioactive Waste Management Conference 2011, Ihlrwmc 2011. 2: 614-620.  1
2011 Jensen KG, Driscoll MJ. Policy issues associated with deep borehole hlw disposal 13th International High-Level Radioactive Waste Management Conference 2011, Ihlrwmc 2011. 2: 914-918.  1
2011 Gibbs JS, Buongiorno J, Driscoll MJ. A multibranch borehole approach to HLW disposal 13th International High-Level Radioactive Waste Management Conference 2011, Ihlrwmc 2011. 2: 608-613.  1
2011 Galle-Bishop JM, Forsberg CW, Driscoll M. Nuclear tanker producing liquid fuels from air and water Transactions of the American Nuclear Society. 104: 589-590.  1
2011 Apostolakis G, Driscoll M, Golay M, Kadak A, Todreas N, Aldemir T, Denning R, Lineberry M. Investigation of risk-informed methodologies to improve sodium-cooled fast reactor economics with safety, and non-proliferation constraints International Topical Meeting On Probabilistic Safety Assessment and Analysis 2011, Psa 2011. 2: 1534-1548.  1
2011 Denman M, Todreas N, Driscoll M. Using importance sampled RELAP5-3D simulations to evaluate radioactive material release frequencies for the technology neutral framework International Topical Meeting On Probabilistic Safety Assessment and Analysis 2011, Psa 2011. 3: 1684-1695.  1
2010 Oloyede IO, Forsberg CW, Driscoll MJ. Gigawatt-year electricity storage requirements for nuclear and renewable power production Transactions of the American Nuclear Society. 103: 567-568.  1
2010 Macdonald RR, Driscoll MJ. Magnesium oxide: An improved reflector for blanket-free fast reactors Transactions of the American Nuclear Society. 102: 488-489.  1
2010 De Witte JD, Todreas NE, Driscoll MJ. Self-actuated shutdown system performance in sodium fast reactors Transactions of the American Nuclear Society. 103: 609-610.  1
2010 Brady PV, Driscoll MJ. Deep borehole disposal of nuclear waste Radwaste Solutions. 17: 58-60.  1
2010 Stauff NE, Driscoll MJ, Forget B, Hejzlar P. Resolution of proliferation issues for a sodium fast reactor blanket Nuclear Technology. 170: 371-382.  1
2010 Denman M, Todreas N, Driscoll M. Creation and verification of an empirical metallic fuel/clad eutectic predictive relationship Transactions of the American Nuclear Society. 103: 482-483.  1
2010 Lee YH, Forsberg C, Driscoll M, Sapiie B. Options for nuclear-geothermal gigawatt-year peak electricity storage systems International Congress On Advances in Nuclear Power Plants 2010, Icapp 2010. 3: 2175-2184.  1
2010 Denman M, Todreas N, Driscoll M. Applying the technology neutral framework to evaluate core outlet temperature changes in a sodium fast reactor International Congress On Advances in Nuclear Power Plants 2010, Icapp 2010. 1: 717-727.  1
2009 Zhang X, Luhrs KJ, Ryff KA, Malik WT, Driscoll MJ, Culver B. Suppression of nuclear factor kappa B ameliorates astrogliosis but not amyloid burden in APPswe/PS1dE9 mice. Neuroscience. 161: 53-8. PMID 19286451 DOI: 10.1016/J.Neuroscience.2009.03.010  0.01
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  1
2009 Shwageraus E, Hejzlar P, Driscoll MJ. Liquid salt cooled flexible conversion ratio fast reactor: Neutronic design Nuclear Engineering and Design. 239: 2626-2645. DOI: 10.1016/J.Nucengdes.2009.07.011  1
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  1
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  1
2009 Pope MA, Lee JI, Hejzlar P, Driscoll MJ. Thermal hydraulic challenges of Gas Cooled Fast Reactors with passive safety features Nuclear Engineering and Design. 239: 840-854. DOI: 10.1016/J.Nucengdes.2008.10.023  1
2009 Matthews IA, Driscoll MJ. A probabilistic projection of future uranium costs Transactions of the American Nuclear Society. 101: 251-252.  1
2009 Denman M, Todreas N, Driscoll M. Risk informed design choices using the technology neutral framework Transactions of the American Nuclear Society. 101: 503-504.  1
2008 Handwerk CS, Driscoll MJ, Hejzlar P. Optimized core design of a supercritical carbon dioxide-cooled fast reactor Nuclear Technology. 164: 320-336. DOI: 10.13182/Nt08-A4030  1
2008 Carstens NA, Vilim RB, Hejzlar P, Driscoll MJ. Dynamic modeling of the S-CO2 recompression cycle International Conference On Advances in Nuclear Power Plants, Icapp 2008. 2: 784-798.  1
2008 McKee SA, Driscoll MJ. An evaluation of vented gas cooled fast reactor fuel Transactions of the American Nuclear Society. 98: 58-60.  1
2007 Forsberg CW, Driscoll MJ. Specialized disposal sites for different reprocessing plant wastes Materials Research Society Symposium Proceedings. 985: 551-556. DOI: 10.1557/Proc-985-0985-Nn13-11  1
2007 Xu Z, Otsuka Y, Hejzlar P, Kazimi MS, Driscoll MJ. High-performance annular fuel reactor physics and fuel management Nuclear Technology. 160: 63-79. DOI: 10.13182/Nt07-A3884  1
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  1
2007 Carstens NA, Hejzlar P, Vilim RB, Driscoll MJ. Inventory control for the S-CO2 recompression cycle Transactions of the American Nuclear Society. 96: 800-801.  1
2007 Gibbs JP, Hejzlar P, Gong Y, Driscoll MJ. Plant layout for a 1200 MWe direct brayton cycle GFR Transactions of the American Nuclear Society. 96: 793-794.  1
2007 Driscoll MJ, Handwerk CS. Multibatch fuel nanagement for gen IV fast reactors Transactions of the American Nuclear Society. 97: 404-405.  1
2007 Lee JI, Hejzlar P, Driscoll MJ. Comparison of experimental depressurization data to RELAP5 results Transactions of the American Nuclear Society. 96: 789-790.  1
2007 Shwageraus E, Hejzlar P, Driscoll MJ. Nuclear design feasibility of a lead-cooled fast reactor with flexible conversion ratio Transactions of the American Nuclear Society. 97: 851-852.  1
2007 Driscoll MJ, Al Hajj-Ahmad A. Supercritical CO2 power conversion system for fusion reactors Transactions of the American Nuclear Society. 96: 777-778.  1
2007 Sizer CG, Hoag CI, Shaikh S, Driscoll MJ. Partitioning and Interment of Selected High Level Wastes Transactions of the American Nuclear Society. 96: 725-726.  1
2007 Handwerk CS, Driscoll MJ, Hejzlar P. Comparison of tube-in-duct and pin fuel for S-CO2 cooled fast reactor applications Transactions of the American Nuclear Society. 96: 654-656.  1
2006 Dostal V, Hejzlar P, Driscoll MJ. High-performance supercritical carbon dioxide cycle for next-generation nuclear reactors Nuclear Technology. 154: 265-282. DOI: 10.13182/Nt154-265  1
2006 Dostal V, Hejzlar P, Driscoll MJ. The supercritical carbon dioxide power cycle: Comparison to other advanced power cycles Nuclear Technology. 154: 283-301. DOI: 10.13182/Nt06-A3734  1
2006 Hejzlar P, Pope MJ, Williams WC, Driscoll MJ. ErratumGas cooled fast reactor for generation IV service [Progress in Nuclear Energy 47 (2005) 271–282] Progress in Nuclear Energy. 48: 184. DOI: 10.1016/J.Pnucene.2005.11.006  1
2006 Memmott MJ, Driscoll MJ, Hejzlar P. Synergistic configuration of a GFR for hydrogen production by steam electrolysis Transactions of the American Nuclear Society. 95: 897-898.  1
2006 Legault DM, Hejzlar P, Driscoll MJ. Effect of pressure drop in brayton cycle efficiency calculations Transactions of the American Nuclear Society. 95: 913-914.  1
2006 Pope MA, Driscoll MJ, Hejzlar P. Shutdown / emergency cooling system for a 2400 MWTH supercritical CO2-cooled direct-cycle GFR Proceedings of the 2006 International Congress On Advances in Nuclear Power Plants, Icapp'06. 2006: 577-589.  1
2006 Hejzlar P, Dostal V, Driscoll MJ. A supercritical CO2 cycle- a promising power conversion system for Generation IV reactors Proceedings of the 2006 International Congress On Advances in Nuclear Power Plants, Icapp'06. 2006: 722-731.  1
2006 Handwerk CS, Driscoll MJ, Hejzlar P. Use of beryllium oxide to shape power and reduce void reactivity in gas cooled fast reactors Physor-2006 - American Nuclear Society's Topical Meeting On Reactor Physics. 2006.  1
2006 Driscoll MJ, Handwerk CS. Tests of a flow-levitated absorber for GFR LOF and LOCA mitigation Transactions of the American Nuclear Society. 94: 567-568.  1
2005 Dhondt AA, Altizer S, Cooch EG, Davis AK, Dobson A, Driscoll MJ, Hartup BK, Hawley DM, Hochachka WM, Hosseini PR, Jennelle CS, Kollias GV, Ley DH, Swarthout EC, Sydenstricker KV. Dynamics of a novel pathogen in an avian host: Mycoplasmal conjunctivitis in house finches. Acta Tropica. 94: 77-93. PMID 15777638 DOI: 10.1016/J.Actatropica.2005.01.009  0.01
2005 Zhang X, Dong F, Ren J, Driscoll MJ, Culver B. High dietary fat induces NADPH oxidase-associated oxidative stress and inflammation in rat cerebral cortex. Experimental Neurology. 191: 318-25. PMID 15649487 DOI: 10.1016/J.Expneurol.2004.10.011  0.01
2005 Xu Z, Kazimi MS, Driscoll MJ. Impact of high burnup on PWR spent fuel characteristics Nuclear Science and Engineering. 151: 261-273. DOI: 10.13182/Nse05-A2545  1
2005 Hejzlar P, Pope MJ, Williams WC, Driscoll MJ. Gas cooled fast reactor for Generation IV service Progress in Nuclear Energy. 47: 271-282. DOI: 10.1016/J.Pnucene.2005.05.077  1
2005 Delaney MJ, Apostolakis GE, Driscoll MJ. Risk-informed design guidance for future reactor systems Nuclear Engineering and Design. 235: 1537-1556. DOI: 10.1016/J.Nucengdes.2005.01.004  1
2005 Yarsky P, Hejzlar P, Driscoll MJ. Reactor physics studies of a breed and burn gas-cooled fast reactor Proceedings of the American Nuclear Society - International Congress On Advances in Nuclear Power Plants 2005, Icapp'05. 1: 153-162.  1
2005 Handwerk CS, Driscoll MJ, Hejzlar P, Yarsky P, Pope MA. Power shaping of a long-lived GFR core using diluents Transactions of the American Nuclear Society. 93: 115-117.  1
2005 Pope MA, Yarsky PJ, Driscoll MJ, Hejzlar P, Saha P. An advanced vented fuel assembly design for GFR applications Transactions of the American Nuclear Society. 92: 211-214.  1
2005 Akkaynak D, Driscoll MJ, Hejzlar P, Apostolakis GE, Golay MW, Cravalho EG. Use of fuel cells to power a high-reliability GFR ECCS Transactions of the American Nuclear Society. 93: 292-293.  1
2005 Yarsky P, Pope MA, Driscoll MJ, Hejzlar P. Reactor physics analysis of a tube-in-duct fuel design for GFR service Transactions of the American Nuclear Society. 92: 694-696.  1
2005 Hejzlar P, Dostal V, Driscoll MJ, Dumaz P, Poullennec G, Alpy N. Assessment of gas cooled fast reactor with indirect supercritical CO 2 cycle Proceedings of the American Nuclear Society - International Congress On Advances in Nuclear Power Plants 2005, Icapp'05. 1: 436-446.  1
2004 Shwageraus E, Zhao X, Driscoll MJ, Hejzlar P, Kazimi MS, Herring JS. Microheterogeneous thoria-urania fuels for pressurized water reactors Nuclear Technology. 147: 20-36. DOI: 10.13182/Nt04-A3512  1
2004 Dostal V, Hejzlar P, Driscoll MJ, Wang Y. Supercritical CO 2 cycle for fast gas-cooled reactors Proceedings of the Asme Turbo Expo 2004. 7: 683-692.  1
2004 Yarsky P, Driscoll MJ, Hejzlar P. Neutronic studies of nuclear fuels for a breed and burn GFR Proceedings of the 2004 International Congress On Advances in Nuclear Power Plants, Icapp'04. 618-623.  1
2004 Williams WC, Hejzlar P, Driscoll MJ. Decay heat removal from a GFR core by natural convection Proceedings of the 2004 International Congress On Advances in Nuclear Power Plants, Icapp'04. 624-636.  1
2004 Saccheri JGB, Todreas NB, Driscoll MJ. A tight lattice, epithermal core design for the integral PWR Proceedings of the 2004 International Congress On Advances in Nuclear Power Plants, Icapp'04. 46-67.  1
2004 Yarsky P, Driscoll MJ, Hejzlar P. Design of a once-through breed and burn GFR Transactions of the American Nuclear Society. 91: 753-755.  1
2004 Pope MA, Driscoll MJ, Hejzlar P. Coolant void reactivity in supercritical CO 2-cooled fast reactors Transactions of the American Nuclear Society. 91: 740-742.  1
2004 Hejzlar P, Williams WC, Driscoll MJ. Hot channel flow starvation of helium cooled GFRs in laminar natural convection Transactions of the American Nuclear Society. 91: 202-204.  1
2004 Yarsky P, Driscoll MJ, Hejzlar P. Use of minimally processed fast reactor fuel in light water reactors Transactions of the American Nuclear Society. 90: 50-51.  1
2004 Driscoll MJ, Hejzlar P, Delaney MJ, Williams WC, Matos C. Compressed gas emergency power supply for GFR service Transactions of the American Nuclear Society. 90: 30-31.  1
2004 Weaver KD, Carbonnier JL, Mizuno T, Rouault J, Wei TYC, Driscoll M. Generation IV nuclear reactors: The gas-cooled fast reactor (GFR) Abstracts of the Pacific Basin Nuclear Conference. 156.  1
2004 Wang Y, Guenette G, Hejzlar P, Driscoll M. Compressor design for the supercritical CO 2 brayton cycle Collection of Technical Papers - 2nd International Energy Conversion Engineering Conference. 3: 1599-1611.  1
2003 Driscoll MJ, Pope MA, Hejzlar P. Self-Actuated Reactivity Insertion Device for GFR Service Transactions of the American Nuclear Society. 89: 573.  1
2003 Carstens NA, Driscoll MJ. LOCA-Powered SCRAM Device for GFRs Transactions of the American Nuclear Society. 89: 576.  1
2003 Driscoll MJ, Pope MA, Hejzlar P. Device for Passive Reactivity Insertion During GFR LOCA Transactions of the American Nuclear Society. 89: 578.  1
2003 Wang D, Kazimi MS, Driscoll MJ, Pilat EE. Optimization of the thorium-uranium seed and blanket core for PWR Global 2003: Atoms For Prosperity: Updating Eisenhowers Global Vision For Nuclear Energy. 1421-1433.  1
2003 Pope MA, Driscoll MJ, Hejzlar P. Reactor physics studies in support of GFR core design Global 2003: Atoms For Prosperity: Updating Eisenhowers Global Vision For Nuclear Energy. 74-81.  1
2003 Yu K, Driscoll MJ, Yarsky PJ, Pope MA, Hejzlar P. Comparison of GFR core reflectors Transactions of the American Nuclear Society. 88: 520.  1
2003 Dostal V, Driscoll MJ, Hejzlar P. A quasi-steady state analysis of the supercritical CO2 recompression Brayton cycle 2003 International Congress On Advances in Nuclear Power Plants - Proceedings of Icapp 2003 1
2003 Driscoll MJ, Hejzlar P. Active or passive post-loca cooling of gfrs? Transactions of the American Nuclear Society. 88: 673.  1
2003 Driscoll MJ, Hejzlar P, Weaver KD, Meyer MK. Basic design choices for a breed and burn fast reactor Transactions of the American Nuclear Society. 88: 678.  1
2002 Xu Z, Driscoll MJ, Kazimi MS. Neutron spectrum effects on burnup, reactivity, and isotopics in UO2/H2O lattices Nuclear Science and Engineering. 141: 175-189. DOI: 10.13182/Nse02-A2277  1
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  1
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  1
2001 Hejzlar P, Driscoll MJ, Kazimi MS. Conceptual neutronic design of a lead-bismuth-cooled actinide burning reactor Nuclear Science and Engineering. 139: 138-155. DOI: 10.13182/Nse01-A2228  1
2001 Byun CS, Jerng DW, Todreas NE, Driscoll MJ. Erratum to “Conceptual design and analysis of a semi-passive containment cooling system for a large concrete containment”: [Nucl. Eng. Des. 199 (2000) 227–242] Nuclear Engineering and Design. 207: 249. DOI: 10.1016/S0029-5493(01)00363-6  1
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  1
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  1
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  1
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  1
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  1
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  1
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  1
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  1
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  1
1996 Hejzlar P, Todreas NE, Driscoll MJ. Passive pressure tube light water reactors Nuclear Technology. 113: 123-133. DOI: 10.13182/Nt96-A35182  1
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  1
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  1
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  1
1994 Tang JR, Todreas NE, Driscoll MJ. Conceptual design features for a passive light water cooled and moderated pressure tube reactor (PLPTR) Nuclear Technology. 107: 49-62. DOI: 10.13182/Nt94-A34997  1
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  1
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  1
1991 Fu G, Driscoll MJ, Todreas NE, Yesilyurt S. Heat transfer and friction factor behavior in the mixed convection regime for air up-flow in a heated vertical pipe Aiche Symposium Series. 87: 326-335.  1
1982 Saragossi II, Driscoll MJ. ADVANCED REACTOR FUEL STRATEGIES - ASSIGNING A VALUE TO PLUTONIUM: METHODOLOGY AND POLICY IMPLICATIONS Transactions of the American Nuclear Society. 40: 236-238.  1
1978 Aminfar H, Driscoll MJ, Salehi AA. USE OF FAST REACTOR METHODS TO GENERATE FEW GROUP CROSS SECTIONS FOR THERMAL REACTORS . 341-349.  1
1977 Torri A, Cerbone RJ, Driscoll MJ. Reactivity insertion mechanisms in the gas-cooled fast breeder reactor Nuclear Engineering and Design. 40: 55-67. DOI: 10.1016/0029-5493(77)90151-0  1
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