A full listing of reports is below. To request a report, please contact Carolyn Carrington at the Center for Advanced Nuclear Energy Systems.
ANP: Advanced Nuclear Power Program
GFR: Gas-cooled Fast Reactors
MRR: Reactor Redesign Program
NES: Nuclear Energy and Sustainability
NFC: Nuclear Fuel Cycle Program
NSA: Nuclear Space Applications
NSP: Nuclear Systems Enhanced Performance
| Program | Type | Number | Revision | Author | Principal Investigator | Title | Month | Year |
|---|---|---|---|---|---|---|---|---|
| ANP | TR | 172 | G. Locatelli (University of Leeds), | WHY ARE MEGAPROJECTS, INCLUDING NUCLEAR POWER PLANTS, DELIVERED OVERBUDGET AND LATE? REASONS AND REMEDIES |
January | 2018 | ||
| ANP | TR | 169 | J. Conway, N. Todreas, | Offshore Floating Nuclear Plant (OFNP): A | July | 2017 | ||
| ANP | TR | 170 | C. W. Forsberg, et al. | Light Water Reactor Heat Storage for Peak Power and Increased Revenue: Focused Workshop on Near-Term Options | July | 2017 | ||
| ANP | TR | 165 | C. Forsberg, D. Carpenter, D. Whyte, R. Scarlat, and L. Wei, | Tritium Control and Capture in Salt-Cooled Fission and Fusion Reactors: Experiments, Models, and Benchmarking | January | 2016 | ||
| ANP | TR | 166 | C. W. Forsberg, S. Lam, D. M. Carpenter, D. G. Whyte, R. Scarlat, C. Contescu, L. Wei, J. Stempien, and E. Blandford, | Tritium Control and Capture in Salt-Cooled Fission and Fusion Reactors: Status, Challenges and Path Forward | May | 2016 | ||
| ANP | TR | 167 | K. Shirvan, G. Daines, K. P. So, A. Mieloszyk, Y. Sukjai, and Ju Li, | Silicon Carbide Performance as Cladding for Advanced Uranium and Thorium Fuels for Light Water Reactors, | August | 2016 | ||
| ANP | TR | 168 | G. N. Genzman, N. Todreas, R. Abeyaratne, and M. Dahleh, | Ship Collision and the Offshore Floating Nuclear Plant (OFNP): Analysis of Possible Threats and Security Measures | September | 2016 | ||
| ANP | TR | 158 | Jacob DeWitte, N.E. Todreas, R. Ballinger, | Maximizing Nuclear Power Plant Performance via Mega-Uprates andSubsequent License Renewal | January | 2015 | ||
| ANP | TR | 159 | Matthew Brian Strother, J. Buongiorno, M.W. Golay, N.E. Todreas, | Hydrodynamic Analysis of the Offshore Floating Nuclear Power Plant | 2015 | |||
| ANP | TR | 160 | J. Jurewicz, J. Buongiorno, M.W. Golay, N.E. Todreas, | Design and Construction of an Offshore Floating Nuclear Power Plant | June | 2015 | ||
| ANP | TR | 161 | A. Briccetti, J. Buongiorno, M.W. Golay. N.E. Todreas, | An Analysis of the Spreading of Radionuclides from a Vent of an Offshore Floating Nuclear Power Plant | 2015 | |||
| ANP | TR | 162 | C. Forsberg, | Strategies for a Low-Carbon Electricity Grid with Full use of Nuclear, Wind and Solar Capacity to Minimize Total Costs | August | 2015 | ||
| ANP | TR | 163 | J. Stempien, R. Ballinger, C. Forsberg, M. Kazimi, | Tritium Transport, Corrosion, and Fuel Performance Modeling in the Fluoride Salt-Cooled High-Temperature Reactor (FHR) | September | 2015 | ||
| ANP | TR | 164 | J. Zhang, J. Buongiorno, M.W. Golay, N.E. Todreas, | Safety Analysis of OFNP-300 and OFNP-1100 (for design basis events) | November | 2015 | ||
| ANP | TR | 149 | Y. Sukjai, E. Pilat, K. Shirvan, and M.S. Kazimi, | Silicon Carbide Performance as Cladding for Advanced Uranium and Thorium Fuels for Light Water Reactors. | January | 2014 | ||
| ANP | TR | 150 | Y-H. Lee, T. McKrell, and M.S. Kazimi, | Safety of Light Water Reactor Fuel with Silicon Carbide Cladding | January | 2014 | ||
| ANP | TR | 151 | M.J. Minck, and C. Forsberg, | Preventing Fuel Failure for a Beyond Design Basis Accident in a Fluoride Salt Cooled High Temperature Reactor | January | 2014 | ||
| ANP | TR | 152 | A. Briccetti, J. Buongiorno, M. Golay, N. Todreas, | Siting of an Offshore Floating Nuclear Power Plant | May | 2014 | ||
| ANP | TR | 153 | C. Forsberg, D. Curtis, J. Stempien, R. MacDonald, P. Peterson, | Fluoride-Salt-Cooled High-Temperature Reactor (FHR) Commercial Basis and Commercialization Strategy. A Fluoride-Salt-Cooled High-Temperature Reactor (FHR) with a Nuclear Air-Brayton Combine Cycle (NACC) and Firebrick Resistance-Heated Energy Storage (FIRES) | December | 2014 | ||
| ANP | TR | 154 | C. Forsberg, L-W. Hu, J. Richard, R. Romatoski, B. Forget, J. Stempien, R. Ballinger, | Fluoride-Salt-Cooled High-Temperature Test Reactor (FHTR): Goals, Options, Ownership, Requirements, Design, Licensing, and Support Facilities | December | 2014 | ||
| ANP | TR | 155 | K. Shirvan, R. Ballinger, J. Buongiorno, C Forsberg, M.S. Kazimi, N.E. Todreas, | Advanced Offshore Seabed Reactors | April | 2014 | ||
| ANP | TR | 156 | Nghia T. Nguyen and Neil E. Todreas, | An Inverted Pressurized Water Reactor Design With Twisted-Tape Swirl | June | 2014 | ||
| ANP | TR | 157 | Charles Forsberg, Lin-Wen Hu, Per Peterson and Kumar Sridharan, | Fluoride-Salt-Cooled High-Temperature Reactor (FHR) for Power and Process Heat | December | 2014 | ||
| ANP | TR | 147 | Forsberg C, Hu L-wen, Peterson PF, Sridharan K. | Fluoride-Salt-Cooled High-Temperature Reactors (FHRs) for Base-Load and Peak Electricity, Grid Stabilization, and Process Heat | June | 2013 | ||
| ANP | TR | 148 | Bloore DA, Pilat EE, Kazimi MS | Reactor Physics Assessment of Thick Silicon Carbide Clad PWR Fuels | July | 2013 | ||
| ANP | TR | 143 | C. Forsberg, L-Wen Hu, P.F. Peterson, and T. Allen, | Fluoride-Salt-Cooled High-Temperature Reactors (FHRs) For Power and Process Heat | January | 2012 | ||
| ANP | TR | 144 | G.L. DeWitt, T. McKrell, L-W Hu, and J. Buongiorno, | Investigation of Downward Facing Critical Heat Flux with Water-Based Nanofluids for In-Vessel Retention Applications | July | 2012 | ||
| ANP | TR | 145 | K. Shirvan and M.S. Kazimi, | Development of Optimized Core Design and Analysis Methods for High Power Density BWRs | November | 2012 | ||
| ANP | TR | 146 | Tingzhou Fei, E. Shwageraus, and M. J. Driscoll, | Innovative Design of Uranium Startup Fast Reactors | November | 2012 | ||
| ANP | TR | 133 | R.C. Petroski and B Forget, | General Analysis of Breed-and-Burn Reactors and Limited-Separations Fuel Cycles | February | 2011 | ||
| ANP | PR | 134 | M.S. Kazimi, J. Dobisesky, D. Carpenter, J. Richards, E. E. Pilat, and E. Shwageraus, | Feasibility and Economic Benefits of PWR Cores with Silicon Carbide Cladding | April | 2011 | ||
| ANP | TR | 135 | J.D. Stempien, D. Carpenter, G. Kohse, and M. S. Kazimi, | Behavior of Triplex Silicon Carbide Fuel Cladding Designs Tested Under Simulated PWR Conditions | June | 2011 | ||
| ANP | TR | 136 | J. Dobisesky, E.E. Pilat, and M. S. Kazimi, | Reactor Physics Considerations for Implementing Silicon Carbide Cladding into a PWR Environment | June | 2011 | ||
| ANP | TR | 137 | B. Truong, L-W Hu, J. Buongiorno, T. McKrell, | Effects of Surface Parameters on Boiling Heat Transfer Phenomena | June | 2011 | ||
| ANP | TR | 138 | F. Vitillo, N.E. Todreas, M.J. Driscoll, | Vented Inverted Fuel Assembly Design for an SFR | June | 2011 | ||
| ANP | TR | 139 | R.P. Arnold, T. McKrell, and M.S. Kazimi, | Vented Silicon Carbide Oxidation in High Temperature Steam | September | 2011 | ||
| ANP | TR | 140 | M.R. Denman, N.E. Todreas and M.J. Driscoll, | Probabilistic Transient Analysis of Fuel Choices for Sodium Fast Reactors | September | 2011 | ||
| ANP | TR | 141 | G. Lenci, N.E. Todreas, M.J. Driscoll and M. Cumo, | Alternatives for Sodium Fast Reactor Cost-Effective Design Improvements | September | 2011 | ||
| ANP | TR | 142 | J. DeWitte and N.E. Todreas, | Reactor Protection System Design Alternatives for Sodium Fast Reactors | September | 2011 | ||
| ANP | TR | 127 | Rui Hu and Mujid S. Kazimi , | Stability Analysis of the Boiling Water Reactor: Methods and Advanced Designs | March | 2010 | ||
| ANP | TR | 128 | Tingzhou Fei and Michael Golay, | Use of Response Surface for Evaluation of Functional Failure of Passive Safety System | March | 2010 | ||
| ANP | TR | 129 | Koroush Shirvan and Mujid S. Kazimi, | The Design of a Compact, Integral, Medium-Sized PWR: The CIRIS | May | 2010 | ||
| ANP | TR | 130 | Yu-Chih Ko and Mujid S. Kazimi | Conceptual Design of an Annular-Fueled Superheat Boiling Water Reactor | October | 2010 | ||
| ANP | TR | 131 | Michael P. Short and Ronald G. Ballinger, | Design of a Functionally Graded Composite for Service in High Temperature Lead and Lead-Bismuth Cooled Nuclear Reactors | October | 2010 | ||
| ANP | TR | 132 | D. M. Carpenter and M. S. Kazimi, | An Assessment of Silicon Carbide as a Cladding Material for Light Water Reactors | November | 2010 | ||
| ANP | TR | 123 | Matthew J. Memmott, Pavel Hejzlar, and Jacopo Buongiorno, | Thermal-Hydraulic Analysis of Innovative Fuel Configurations for the Sodium Fast Reactor | August | 2009 | ||
| ANP | TR | 124 | Joshua J. Whitman and Mujid S. Kazimi, | Thermal Hydraulic Design Of A Salt-Cooled Highly Efficient Environmentally Friendly Reactor | August | 2009 | ||
| ANP | TR | 125 | M.S. Kazimi, P. Hejzlar, Y. Shatilla, Bo Feng, Yu-Chih Ko, E. Pilat, K. Shirvan, J. Whitman, and A. Hamed, | A High Efficiency and Environmentally Friendly Nuclear Reactor (HEER) for Electricity and Hydrogen | October | 2009 | ||
| ANP | TR | 125 | v. 1 | M.S. Kazimi, P. Hejzlar, Y. Shatilla, Bo Feng, Yu-Chih Ko, E. Pilat, K. Shirvan, J. Whitman, and A. Hamed, | M.S. Kazimi & P. Hejzlar (MIT), Y. Shatilla (MIST) | A High Efficiency and Environmentally Friendly Nuclear Reactor (HEER) for Electricity and Hydrogen Volume I: Main Report |
November | 2009 |
| ANP | TR | 125 | v. 2 | M.S. Kazimi, P. Hejzlar, Y. Shatilla (MIST), Bo Feng, Yu-Chih Ko, E. Pilat, K. Shirvan, J. Whitman, and A. Hamed (MIST) | M.S. Kazimi & P. Hejzlar (MIT), Y. Shatilla (MIST) | A High Efficiency and Environmentally Friendly Nuclear Reactor (HEER) for Electricity and Hydrogen Volume I: Appendices |
November | 2009 |
| ANP | TR | 126 | Paolo Ferroni and Neil E. Todreas, | An Inverted Hydride-Fueled Pressurized Water Reactor Concept | October | 2009 | ||
| ANP | TR | 119 | M.J. Driscoll | Comparative Economic Prospects of the Supercritical CO₂ Brayton Cycle GFR | February | 2008 | ||
| ANP | TR | 120 | Jiyong Oh and M.W. Golay | Methods for Comparative Assessment of Active and Passive Safety Systems | February | 2008 | ||
| ANP | TR | 121 | M. Memmott, J. Buongiorno, and P. Hejzlar, | Development and Validation of a Flexible RELAP5-3D-Based Subchannel Analysis Model for Fast Reactor Fuel Assemblies | December | 2008 | ||
| ANP | TR | 122 | Sung Joong Kim, T. McKrell, J. Buongiorno, Lin-wen Hu, | Subcooled Flow Boiling Heat Transfer and Critical Heat Flux in Water-Based Nanofluids at Low Pressure | April | 2008 | ||
| ANP | TR | 113 | C.S. Handwerk, P. Hejzlar, and M.J. Driscoll | Core Design and Performance Assessment for a Supercritical CO2-Cooled Fast Reactor | May | 2007 | ||
| TR | 114 | N.A. Carstens, P. Hejzlar, and M.J. Driscoll | Dynamic Response and Safety Implications for Supercritical CO2 Brayton Cycles Coupled to Gen-IV Reactors | July | 2007 | |||
| ANP | TR | 115 | J. Lee, P. Hejzlar, M.S. Kazimi | Deteriorated Turbulent Heat Transfer to Up-Flowing Gas in a Heated Vertical Channel | May | 2007 | ||
| ANP | TR | 116 | R. Hannink, J. Buongiorno, L. Hu, G. Apostolakis | Using Nanofluids to Enhance the Capability of In-Vessel Retention of Fuel Following Severe Reactor Accidents | June | 2007 | ||
| ANP | TR | 118 | R. Hu, M.S. Kazimi | Stability Analysis of Natural Circulation in BWRs at High Pressure Conditions | October | 2007 | ||
| ANP | TR | 110 | B.D. Middleton and J. Buongiorno | Supercritical Water Reactor Cycle for Medium Power Applications | June | 2006 | ||
| ANP | PR | 111 | R. Eul, K. Ahn, S.P. Kao, P. Hejzlar, and M.S. Kazimi | A Comparison of Passive vs. Active Safety Systems for Advanced Light Water Reactors | September | 2006 | ||
| ANP | TR | 111 | R. Eul, K. Ahn, S.P. Kao, P. Hejzlar, and M.S. Kazimi, | A Comparison of Passive vs. Active Safety Systems for Advanced Light Water Reactors | September | 2006 | ||
| ANP | TR | 112 | M.A. Pope, P. Hejzlar, and M.J. Driscoll, | Thermal Hydraulics of a 2400 MWth Supercritical CO2-Direct Cycle GFR | September | 2006 | ||
| ANP | TR | 107 | P. Yarsky, M.J. Driscoll, and P. Hejzlar | Integrated Design of a Breed and Burn Gas-cooled Fast Reactor Core | September | 2005 | ||
| ANP | TR | 108 | J. Zhao, P. Saha, and M.S. Kazimi | Stability Analysis of Supercritical Water Cooled Reactors | September | 2005 | ||
| ANP | TR | 109 | C. Gerardi and J. Buongiorno | Investigation of Pressure Tube and Calandria Tube Deformation Following a Single Channel Blockage Event in ACR-700 | November | 2005 | ||
| ANP | TR | 3 | A. Bushman, D.M. Carpenter, T.S. Ellis, S.P. Gallagher, M.D. Hershcovitch, M.C. Hine, E.D. Johnson, S.C. Kane, M.R. Presley, A.H. Roach, S. Shaikh, M.P. Short, and M.A. Stawicki | The Martian Surface Reactor: An Advanced Nuclear Power Station for Manned Extraterrestrial Exploration | December | 2004 | ||
| ANP | TR | 100 | V. Dostal, M.J. Driscoll, and P. Hejzlar | A Super Critical Carbon Dioxide Cycle for Next Generation Nuclear Reactors | March | 2004 | ||
| ANP | TR | 101 | J. Wang, R. Ballinger, and S. Yip | An Integrated Performance Model for High Temperature Gas Cooled Reactor Coated Particle Fuel | March | 2004 | ||
| ANP | TR | 102 | T. Zhai, A. Kadak, and H.C. No | LOCA and Air Ingress Accident Analysis of a Pebble Bed Reactor | March | 2004 | ||
| ANP | TR | 103 | K. Gezelius, M.J. Driscoll, and P. Hejzlar | Design of Compact Intermediate Heat Exchangers for Gas Cooled Fast Reactors | May | 2004 | ||
| ANP | TR | 104 | M.A. Pope, M. Driscoll, and P. Hejzlar | Reactor Physics Design of Supercritical CO2-Cooled Fast Reactors | September | 2004 | ||
| ANP | TR | 105 | J. Zhao, P. Saha, and M.S. Kazimi | Analysis of Flow Instabilities in Supercritical Water-Cooled Nuclear Reactors | October | 2004 | ||
| ANP | TR | 106 | G. Jourdan and M. Golay | Using Risk-Based Regulations for Licensing Nuclear Power Plants: Case Study of the Gas-cooled Fast Reactor | December | 2004 | ||
| ANP | TR | 86 | K. Yu, M.J. Driscoll, and P. Hejzlar | Neutronic Evaluation of GCFR Core Diluents | June | 2003 | ||
| ANP | TR | 87 | M.J. Driscoll, P. Hejzlar, N.E. Todreas, and B. Veto | Modern Gas-Cooled Fast Reactor Safety Assurance Considerations | May | 2003 | ||
| ANP | TR | 95 | W. Williams, P. Hejzlar, M.J. Driscoll, N.E. Todreas, P. Saha, and W.J. Lee | Analysis of a Convection Loop for GFR Post-LOCA Decay Heat Removal | March | 2003 | ||
| ANP | TR | 96 | J.G.B. Saccheri and N.E. Todreas | A Tight Lattice, Epithermal Core Design for the IRIS Reactor | May | 2003 | ||
| ANP | TR | 97 | J.G.B. Saccheri, N.E. Todreas, and M.J. Driscoll | A Tight Lattice, Epithermal Core Design for the Integral PWR, Vol I | August | 2003 | ||
| ANP | TR | 97 | J.G.B. Saccheri, N.E. Todreas, and M.J. Driscoll | A Tight Lattice, Epithermal Core Design for the Integral PWR, Vol II - Appendices | December | 2003 | ||
| ANP | TR | 99 | S. Blair and N.E. Todreas | Thermal Hydraulic Performance Analysis of a Small Integral Pressurized Water Reactor Core | December | 2003 | ||
| ANP | TR | 85 | V. Dostal, N.E. Todreas, P. Hejzlar, and M.S. Kazimi | Power Conversion Cycle Selection for the LBE Cooled Reactor with Forced Circulation | February | 2002 | ||
| ANP | TR | 88 | Y. Okano, P. Hejzlar, N.E. Todreas, and M.J. Driscoll | Thermal Hydraulics and Shutdown Cooling of Supercritical CO2 GT-GCFRs | August | 2002 | ||
| ANP | TR | 89 | J.E. Withee and M.W. Golay | Deterministic Causality Analysis of the Pebble Bed Modular Reactor for Use with Risk-Based Safety Regulation | August | 2002 | ||
| ANP | TR | 90 | V. Dostal, M.J. Driscoll, P. Hejzlar, and N.E. Todreas | CO2 Brayton Cycle Design and Optimization | November | 2002 | ||
| ANP | PR | 92 | Rev. 1 | P.E. MacDonald, N.E. Todreas, J. Buongiorno et al. | Design of an Actinide Burning, Lead or Lead-Bismuth Cooled Reactor That Produces the Low Cost Electricity, FY-02 Annual Report | October | 2002 | |
| ANP | PR | 93 | M.J. Driscoll, P. Hejzlar, N.E. Todreas, Y. Okano, V. Dostal, and K. Yu | Development of Gen IV Advanced Gas-Cooled Reactors with Hardened/Fast Neutron Spectrum, Annual Progress Report | September | 2002 | ||
| ANP | PR | 94 | A.C. Kadak, R.G. Ballinger et al. | Modular Pebble Bed Reactor Project, Fourth Annual Report | December | 2002 | ||
| ANP | TR | 77 | T.A. Galen, D.G. Wilson, and A.C. Kadak | Comparison Between Air and Helium for Use as Working Fluids in the Energy-Conversion Cycle of the MPBR | February | 2001 | ||
| ANP | TR | 79 | J. Buongiorno, N.E. Todreas, M.S. Kazimi, and K.R. Czerwinski | Conceptual Design of a Lead-Bismuth Cooled Fast Reactor with In-Vessel Direct-Contact Steam Generation | March | 2001 | ||
| ANP | TR | 80 | R.G. Ballinger, J.Y. Lim, and M.S. Kazimi | A Review of US Research Activities on Material Compatibility Issues in Nuclear Systems Using Heavy Liquid-Metal Coolant and Needs for Improved Materials | July | 2001 | ||
| ANP | TR | 81 | P. Hejzlar, M.J. Driscoll, N.E. Todreas, and M.S. Kazimi | Evaluation of a Once-Through Lead-Bismuth-Cooled Reactor Concept | September | 2001 | ||
| ANP | TR | 82 | V. Dostal, P. Hejzlar, N.E. Todreas, and M.S. Kazimi | Plant Design and Cost Assessment of Forced Circulation Lead-Bismuth Cooled Reactor with Conventional Power Conversion Cycles | September | 2001 | ||
| ANP | PR | 83 | P.E. MacDonald, N.E. Todreas, J. Buongiorno et al. | Design of an Actinide Burning, Lead or Lead-Bismuth Cooled Reactor that Produces the Low Cost Electricity, FY-01 Annual Report | October | 2001 | ||
| ANP | PR | 84 | A.C. Kadak, R.G. Ballinger et al. | Modular Pebble Bed Reactor Project, Third Annual Report | November | 2001 | ||
| ANP | PR | 92 | P.E. MacDonald, N.E. Todreas, J. Buongiorno et al. | Design of an Actinide Burning, Lead or Lead-Bismuth Cooled Reactor That Produces the Low Cost Electricity, FY-02 Annual Report | October | 2001 | ||
| ANP | TR | 69 | P. Hejzlar, M.J. Driscoll, and M.S. Kazimi | Conceptual Reactor Physics Design of a Lead-Bismuth-Cooled Critical Actinide Burner | February | 2000 | ||
| ANP | TR | 70 | J.R. Lebenhaft and M.J. Driscoll | Physics Benchmark Analysis of the HTR-10 Reactor Using the Monte Carlo Code MCNP | March | 2000 | ||
| ANP | TR | 71 | A. Romano and N.E. Todreas | Selection of Correlations and Look-Up Tables for Critical Heat Flux Prediction in the Generation IV "IRIS" Reactor | June | 2000 | ||
| ANP | PR | 71 | J. Buongiorno, N. Todreas et al | Design of an Actinide Burning, Lead or Lead-Bismuth Cooled Reactor that Produces Low Cost Electricity | July | 2000 | ||
| ANP | TR | 72 | J. Buongiorno, P. Hejzlar, N.E. Todreas et al. | Design of Lead-Bismuth Cooled Reactors for Actinide Burning and for Low Cost Electricity | June | 2000 | ||
| ANP | TR | 73 | A. Romano and N.E. Todreas | Analysis of Novel Fuel Geometries for the Generation IV "IRIS" Reactor | June | 2000 | ||
| ANP | TR | 74 | D. Kim, N.E. Todreas, M.S. Kazimi, and M.J. Driscoll | Plant Design and Cost Estimation of a Natural Circulation Lead-Bismuth Reactor with Steam Power Conversion Cycle | August | 2000 | ||
| ANP | PR | 75 | A.C. Kadak, R.G. Ballinger et al. | Modular Pebble Bed Reactor Project: Second Annual Report | July | 2000 | ||
| ANP | TR | 76 | D. Kim, N.E. Todreas, M.S. Kazimi, and M.J. Driscoll | Plant Design and Cost Estimation of a Natural Circulation Lead-Bismuth Reactor with Helium Power Conversion Cycle | November | 2000 | ||
| ANP | TR | 78 | L.C. Doboe, Jr., N.E. Todreas, and M.W. Golay | The Role of Uncertain Consequences in Nuclear Power Investment Decision Making | September | 2000 | ||
| ANP | TR | 55 | Part II | B.T. Mattingly, N.E. Todreas, and M.J. Driscoll | MIT Advanced Containment Project: Containment Analysis Incorporating Boundary Layer Heat and Mass Transfer Techniques, Part II | February | 1999 | |
| ANP | TR | 61 | H.Y. Liu, N.E. Todreas, and M.J. Driscoll | An Experimental Investigation of A Passive Cooling Unit for Nuclear Plant Containment | February | 1999 | ||
| ANP | TR | 62 | C.S. Byun, D.W. Jerng, N.E. Todreas, and M.J. Driscoll | Conceptual Design and Distributed Parameter Analysis of a Semi-passive Containment Cooling System for a Large Dry Concrete Containment | February | 1999 | ||
| ANP | TR | 63 | H. Liu and N.E. Todreas | A Semi-Passive Containment Cooling System Conceptual Design, Final Report | March | 1999 | ||
| ANP | TR | 64 | K. Tezuka and M.W. Golay | Reliability-Based Nuclear Power Plant Maintenance Resource Allocation in Order to Reduce Unfavorable Operational Publicity | June | 1999 | ||
| ANP | TR | 64 | F. Li, M.W. Golay, N.E. Todreas | Efficient Investment Allocation for Improving Nuclear Power Plant Performance | May | 1999 | ||
| ANP | TR | 65 | J. Buongiorno, P. Hejzlar, N.E. Todreas et al. | Design of an Actinide Burning, Lead-Bismuth Cooled Reactor That Produces Low Cost Electricity | June | 1999 | ||
| ANP | TR | 66 | J. Buongiorno, N.E. Todreas, and M.S. Kazimi | Thermal Design of Lead-Bismuth Cooled Reactor for Actinide Burning and Power Production | July | 1999 | ||
| ANP | TR | 68 | P. Hejzlar, M.J. Driscoll, and M.S. Kazimi | Void Reactivity Performance in Lead-Bismuth-Cooled Reactor for Actinide Transmutation | August | 1999 | ||
| ANP | TR | 57 | Vol. 1 | M.W. Golay, C.W. Kang, J.B. Lee, and Y. Sui | On-Line Monitoring for Improved Nuclear Power Plant Availability and Operational Advice | February | 1998 | |
| ANP | TR | 58 | S. Utton and M.W. Golay | Risk-Informed, Performance-Based Regulatory Implications of Improved Emergency Diesel Generator Reliability | January | 1998 | ||
| ANP | TR | 59 | Y.H. Kim, N.E. Todreas, and M.J. Driscoll | Distributed Parameter Modeling of the KNGR Containment using GOTHIC | January | 1998 | ||
| ANP | TR | 60 | M.W. Golay, J.D. Dulik, F.A. Felder, and S.M. Utton | Project on Integrated Models, Data Bases and Practices Needed for Performance-Based Safety Regulation, Final Report | December | 1998 | ||
| ANP | TR | 49 | C.S. Handwerk, M.J. Driscoll, N.E. Todreas, and M.V. McMahon | Economic Analysis of Implementing a Four-Year Extended Operating Cycle in Existing PWRs | January | 1997 | ||
| ANP | TR | 51 | R.S. McHenry and N.E. Todreas | Nuclear Power Plant Surveillance Issues for Extended Operating Cycles | February | 1997 | ||
| ANP | TR | 52 | C.W. Kang and N.E. Todreas | A Strategy for Reducing the Forced Outage Rates of Reactor Coolant Pumps for a 48-Month Operating Cycle | August | 1997 | ||
| ANP | TR | 53 | Vol. I, Rev. 1 | M. Leiendecker, N.E. Todreas, and M.J. Driscoll | Design and Numerical Simulation of a Two-Phase Thermosyphon Loop as a Passive Containment Cooling System for PWRs, Rev. 1, Vol. I | September | 1997 | |
| ANP | TR | 53 | Vol. II, Rev. 1 | M. Leiendecker, N.E. Todreas, and M.J. Driscoll | Design and Numerical Simulation of a Two-Phase Thermosyphon Loop as a Passive Containment Cooling System for PWRs, Rev. 1, Vol. II | September | 1997 | |
| ANP | TR | 54 | Y.H. Kim, N.E. Todreas, and M.J. Driscoll | Lumped Parameter Modeling of the KNGR Containment Using GOTHIC | July | 1997 | ||
| ANP | TR | 55 | Part I | B.T. Mattingly and N.E. Todreas | MIT Advanced Containment Project: Review of Condensation Models and Computer Code Evaluation, Part I | July | 1997 | |
| ANP | TR | 56 | J.D. Dulik and M.W. Golay | Use of Performance Monitoring to Improve Reliability of Emergency Diesel Generators | December | 1997 | ||
| ANP | TR | 36 | T.J. Moore, J.H. Maurer, R.S. McHenry, and N.E. Todreas | Surveillance Strategy for a Four-Year Operating Cycle in Commercial Nuclear Reactors | June | 1996 | ||
| ANP | TR | 40 | J.R. Lunglhofer, M.W. Golay, and D.D. Lanning | Complete Safety Software Testing: A Formal Method | January | 1996 | ||
| ANP | TR | 41 | H. Masui and M.W. Golay | Quantitative Methodology for Surveillance Interval Extension at Nuclear Power Plants | June | 1996 | ||
| ANP | TR | 42 | T.L. Stoops and M.W. Golay | An Investigation of How Powerful a Nuclear Reactor Can Be | June | 1996 | ||
| ANP | TR | 43 | F. Li and M.W. Golay | A Study for Improving Reliability and Capacity Factor of the PWR Feedwater Supply System | June | 1996 | ||
| ANP | TR | 44 | T.J. Moore and N.E. Todreas | A Strategy for Reducing Forced Outage Rates in Commercial Nuclear Reactors with a Main Feed Pump Case Study | July | 1996 | ||
| ANP | TR | 45 | M.V. McMahon, M.J. Driscoll, and N.E. Todreas | Modeling and Design of a Reload PWR Core for a 48-Month Fuel Cycle | July | 1996 | ||
| ANP | TR | 46 | N.E. Todreas and M.V. McMahon | Improvement in Nuclear Plant Capacity Factors Through Longer Cycle Length Operation, Annual Report | July | 1996 | ||
| ANP | TR | 47 | J. Automo and M.W. Golay | Dependency of Human Operator Performance Quality upon Task Complexity | September | 1996 | ||
| ANP | TR | 48 | M. Leiendecker, N.E. Todreas, M.J. Driscoll, and A. Hurtado | Passive Containment Cooling System for Large PWRs Using Thermosyphon Loops | October | 1996 | ||
| ANP | TR | 50 | N.E. Todreas, M.J. Driscoll, P. Hejzlar, B. Mattingly, and G. Dalporto | Conceptual Design of a Water Cooled Reactor with Passive Decay Heat Removal, Final Performance Technical Report | November | 1996 | ||
| ANP | TR | 29 | X. Chen and N.E. Todreas | Thermal Analysis of Dry Spent Fuel Transportation and Storage Casks | January | 1995 | ||
| ANP | TR | 30 | G. Dalporto and N.E. Todreas | Achieving Higher Capacity Factors in Nuclear Power Plants Through Longer Operating Cycles | February | 1995 | ||
| ANP | TR | 31 | B.T. Mattingly, P. Hejzlar, N.E. Todreas, and M.J. Driscoll | Fuel Matrices for the Passive Pressure Tube Light Water Reactor | March | 1995 | ||
| ANP | TR | 32 | A.F.A. Ayoub and M.J. Driscoll | A Strategy for Extending Cycle Length to Improve Pressurized Water Reactor Capacity Factor | June | 1995 | ||
| ANP | TR | 33 | J. Novak, N.E. Todreas, and M.J. Driscoll | Conception and Experimental Investigation of Thermal Switches | June | 1995 | ||
| ANP | TR | 34 | M. Gavrilas, N.E. Todreas, and M.J. Driscoll | Alternative Passive Cooling Concepts for a Large Rating Pressurized Water Reactor Containment | August | 1995 | ||
| ANP | TR | 35 | M. Ouyang and M.W. Golay | An Integrated Formal Approach for Developing High Quality Software for Safety-Critical Systems | September | 1995 | ||
| ANP | TR | 37 | A.A. Dehbi, M.W. Golay, and M.S. Kazimi | The Performance Study of the Tube Water Wall PCCL and an Experimental Correlation for Steam Condensation in the Presence of Air Under Natural Convection | September | 1995 | ||
| ANP | TR | 38 | C. Lapp and M.W. Golay | A Methodology for Modular Nuclear Power Plant Design and Construction | October | 1995 | ||
| ANP | TR | 39 | C.W. Kang, M. Ouyang, and M.W. Golay | A Mental Procedure for More Reliable Specification of System Control Software Requirements | December | 1995 | ||
| ANP | TR | 19 | K.E. Poorman, M.W. Golay, and D.D. Lanning | On the Complete Testing of Simple, Safety-Related Software | February | 1994 | ||
| ANP | TR | 20 | A.R. Patel, N.E. Todreas, and M.J. Driscoll | Integrated Containment/Hyperbolic Cooling Tower System | January | 1994 | ||
| ANP | TR | 21 | P. Hejzlar, N.E. Todreas, and M.J. Driscoll | Special Computer Codes and Supplementary Data for the Conceptual Design of a Large, Passive, Pressure-tube LWR | May | 1994 | ||
| ANP | TR | 22 | M.G. Arno and M.W. Golay | Verification and Validation of Safety Related Software | June | 1994 | ||
| ANP | TR | 23 | P. Hejzlar, N.E. Todreas, and M.J. Driscoll | Conceptual Design of a Large, Passive Pressure-Tube Light Water Reactor | June | 1994 | ||
| ANP | TR | 24 | H.A. Hasanein, M.W. Golay, and M.S. Kazimi | Steam Condensation in the Presence of Noncondensable Gases under Forced Convection Conditions | July | 1994 | ||
| ANP | TR | 25 | P. Hejzlar, N.E. Todreas, and M.J. Driscoll | Technical Summary of a Conceptual Design of a Large, Passive Pressure-Tube Light Water Reactor | July | 1994 | ||
| ANP | TR | 26 | E.M. Hermanson and M.W. Golay | The Dependence of Human Reliability Upon Task Information Content | August | 1994 | ||
| ANP | TR | 27 | J.T. Hwang, N.E. Todreas, and M.J. Driscoll | Experimental Evaluation of a Passive Water Cooled Containment Concept | August | 1994 | ||
| ANP | TR | 28 | M. Ouyang and M.W. Golay | Comparative Performance Evaluation of an Advanced Semi-Passive and an Evolutionary Pressurized Water Reactor Nuclear Power Plants in the Loss of Offsite Power Event | December | 1994 | ||
| ANP | TR | 15 | C.H. Kang and M.S. Kazimi | Transmutation Effects on Transuranic Waste Inventory and Its Repository Risk | March | 1993 | ||
| ANP | TR | 16 | P. Hejzlar, N.E. Todreas, M.J. Driscoll, and B. Mattingly | Conceptual Design of a Water Cooled Reactor with Passive Decay Heat Removal, DOE Progress Report | May | 1993 | ||
| ANP | TR | 17 | P. Hejzlar, N.E. Todreas, and M.J. Driscoll | Evaluation of Materials for the Pressure Tube Matrix of a Passive LWR Concept | November | 1993 | ||
| ANP | TR | 18 | H. Khan and M.J. Driscoll | An Evaluation of Passive Spray Cooling for Nuclear Reactor Containments | September | 1993 | ||
| ANP | TR | 10 | M. Siddique, M.W. Golay, and M.S. Kazimi | The Effects of Noncondensable Gases on Steam Condensation under Turbulent Natural Convection Conditions | March | 1992 | ||
| ANP | TR | 11 | N.S. Qureshi and M.W. Golay | A Sensitivity Analysis of the Role of Human Actions for the Loss of Offsite Power Scenario | May | 1992 | ||
| ANP | TR | 12 | W.W. Schenler and M.W. Golay | ORNL/MIT Technical Support Tasks for USDOE/MITNE Integral Fast Reactor Program: Task 2, Environmental Impact Assessment | May | 1992 | ||
| ANP | TR | 13 | Vol. I | J.R. Tang, N.E. Todreas, and M.J. Driscoll | Conceptual Design of the Passive Light Water Cooled and Moderated Pressure Tube Reactor (PLPTR), Vol. I | August | 1992 | |
| ANP | TR | 13 | Vol. II | J.R. Tang, N.E. Todreas, and M.J. Driscoll | Conceptual Design of the Passive Light Water Cooled and Moderated Pressure Tube Reactor (PLPTR), Volume II | August | 1992 | |
| ANP | TR | 14 | A. Schneider and D. Freed | Integral Fast Reactor-Related Research‚ Subtask 1C: Analysis of IFR Demonstration Program, Final Report | June | 1992 | ||
| ANP | TR | 2 | M.G. Houts and D.D. Lanning | Out-of-Core Thermionic Space Nuclear Reactors: Design and Control Considerations | January | 1991 | ||
| ANP | TR | 3 | P. Hejzlar, N.E. Todreas, and M.J. Driscoll | Passive Decay Heat Removal in Advanced Reactor Concepts, Vols I & II | May | 1991 | ||
| ANP | TR | 3 | Vol. II Appendices | P. Hejzlar, N.E. Todreas, and M.J. Driscoll | Passive Decay Heat Removal in Advanced Reactor Concepts, Vol. II | May | 1991 | |
| ANP | TR | 4 | A.A. Dehbi, M.W. Golay, and M.S. Kazimi | The Effects of Non-Condensable Gases on Steam Condensation under Turbulent Natural Convection Conditions | June | 1991 | ||
| ANP | TR | 6 | A.A. Dehbi, M.W. Golay, and M.S. Kazimi | Passive Containment Cooling for a 900 MWe Reactor | August | 1991 | ||
| ANP | TR | 7 | W.R. Hollaway and L.M. Lidsky | The Combined Hybrid System‚ A Symbiotic Thermal Reactor/Fast Reactor System for Power Generation and Radioactive Waste Toxicity Reduction | August | 1991 | ||
| ANP | TR | 8 | J.R. Tang, N.E. Todreas, and M.J. Driscoll | Concepts for a Pressure Tube Light Water Reactor with Passive Safety Features | September | 1991 | ||
| ANP | TR | 9 | J.R. Tang, M.J. Driscoll, and N.E. Todreas | Physics Considerations in a Passive Light Water Pressure Tube Reactor (PLPTR) | November | 1991 | ||
| ANP | CP | 1 | Proceedings of the First MIT International Conference on the Next Generation of Nuclear Power Technology | October | 1990 | |||
| ANP | TR | 1 | W.R. Hollaway, L.M. Lidsky, and M.M. Miller | The Role of Actinide Burning and the Integral Fast Reactor in the Future of Nuclear Power | December | 1990 | ||
| ANP | TR | 5 | J.C. Han, M.J. Driscoll, and N.E. Todreas | The Effective Thermal Conductivity of Prismatic MHTGR Fuel | September | 1989 | ||
| ANP | TR | 91 | R. Herron, N.E. Todreas, and P. Hejzlar | Component Design and Capital Cost Analysis of a Forced Circulation Lead-Bismuth Eutectic Cooled Nuclear Reactor | To be published | |||
| ANP | TR | 98 | J.A. Malen and N.E. Todreas | Thermal Hydraulic Design of Hydride Fueled Pressurized Water Reactor Cores | To be published | |||
| Program | Number | Author | Principal Investigator | Title | Month | Year |
|---|---|---|---|---|---|---|
| GFR | 43 | S.A. McKee | M.J. Driscoll | Assessment of Fuel Assembly Venting for Supercritical CO2 Cooled Fast Reactors | May | 2008 |
| GFR | 45 | M.J. Driscoll, P. Hejzlar, G. Apostolakis | Optimized, Competitive Supercritical-CO2 Cycle GFR for Gen IV Service Final Report | September | 2008 | |
| GFR | 34 | Y. Gong, N.A. Carstens, M.J. Driscoll, I.A. Matthews | M.J. Driscoll | Analysis of Radial Compressor Options for Supercritical CO₂ Power Conversion Cycles | June | 2006 |
| GFR | 38 | N.A. Carstens, P. Hejzlar, M.J. Driscoll | Control System Strategies and Dynamic Response for Supercritical CO₂ Power Conversion Cycles | September | 2006 | |
| GFR | 40 | D. Langewisch, S-P. Kao, M.J. Driscoll | HXMOD - A Heat Exchanger Module for Power Cycle Dynamics Modeling | August | 2006 | |
| GFR | 41 | I.A. Matthews | M.J. Driscoll, Y. Gong | Characterization of Radial Compressors for Supercritical CO₂ Power Conversion Systems | September | 2006 |
| GFR | 22 | Y. Wang, G.R. Guenette, P. Hejzlar, M.J. Driscoll | M.J. Driscoll, P. Pickard (Sandia National Laboratories) | Aerodynamic Design of Turbomachinery for 300 Mwe Supercritical Carbon Dioxide Brayton Power Conversion System | March | 2005 |
| GFR | 25 | P.W. Stahle, M.J. Driscoll, P. Hejzlar | M.J. Driscoll, P. Pickard (Sandia National Laboratories) | Supercritical CO₂ Power Conversion System Design and Layout for 300 Mwe Plant | September | 2005 |
| GFR | 26 | P. Hejzlar, S.J. Kim, W.C. Williams | Transient ATHENA/RELAP-3D Calculations for a 600MWth Plate-type Helium GFR | April | 2005 | |
| GFR | 27 | N.A. Carstens, P. Hejzlar, M.J. Driscoll | M.J. Driscoll, P. Pickard (Sandia National Laboratories) | Description of Supercritical CO₂ Systems Control Model | September | 2005 |
| GFR | 28 | Y. Gong, N.A. Carstens, M.J. Driscoll | M.J. Driscoll, P. Pickard (Sandia National Laboratories) | Supercritical CO₂ Cycle Main Compressor Design and Analysis Studies | September | 2005 |
| GFR | 29 | H. Funmilayo, M.J. Driscoll, Y. Gong, G. Guenette | M.J. Driscoll, P. Pickard (Sandia National Laboratories) | Design of Small Scale Supercritical CO₂ Brayton Cycle Experiment, Including Main Compressor Test Capability | August | 2005 |
| GFR | 30 | N. Carstens | M.J. Driscoll, P. Pickard (Sandia National Laboratories) | Props 1.5: A Command Line Fluid Properties Code | August | 2005 |
| GFR | 31 | N. Carstens | M.J. Driscoll, P. Pickard (Sandia National Laboratories) | Turbomap 1.2: A Command Line Turbomachinery Map Code | September | 2005 |
| GFR | 32 | Y. Wang | Estimation of N-16 Dose Rate for Direct Cycle CO₂ Gas Cooled Fast Reactors | August | 2005 | |
| GFR | 35 | M. Driscoll, K. Czerwinski, P. Hejzlar, P. Saha | M. Driscoll, K. Weaver (Idaho National Lab), M. Meyer (Idaho National Lab) | Engineering and Physics Optimization of Breed and Burn Fast Reactor Systems | December | 2005 |
| GFR | 8 | M.J. Delaney, C. Matos, B.T. Parks, J.P. Koser | Interim Report on Task 1: GFR PRA-Guided Plant Design Annual Report on Project: Plant Design and Core Materials Compatibility Studies for Supercritical CO₂ Cooled Reactors |
March | 2004 | |
| GFR | 10 | D. Rigual, P. Stahle, Y. Ostrovsky, G. Kohse, Y.H. Jeong, R. Ballinger | R.G. Ballinger, M.J. Driscoll, K.D. Weaver (Idaho National Laboratory) | Interim Report on Task 2: Loops for Corrosion Tests in Supercritical CO₂ in the Presence of Radiolysis Annual Report on Project: Plant Design and Core Materials Compatibility Studies for Supercritical CO₂ Cooled Reactors |
March | 2004 |
| GFR | 11 | J. Plaue and K.R. Czerwinski | K.R. Czerwinski, M.J. Driscoll, K.S. Weaver (Idaho National Laboratory) | Interim Report on Task 3: Fuel Material Interactions Annual Report on Project: Plant Design and Core Materials Compatibility Studies for Supercritical CO₂ Cooled Reactors |
March | 2004 |
| GFR | 12 | Y. Wang, V. Dostal, M.J. Driscoll, P. Hejzlar, G.R. Guenette | M.J. Driscoll, P. Pickard (Sandia National Laboratories) | Annual Report - Qualification of the Supercritical CO₂ Power Conversion Cycle for Advanced Reactor Applications | April | 2004 |
| GFR | 13 | M.J. Delaney, G.E. Apostolakis, M.J. Driscoll | Risk-Informed Design Guidance for a Generation-IV Gas-Cooled Fast Reactor Emergency Core Cooling System | May | 2004 | |
| GFR | 14 | M.J. Driscoll & P. Hejzlar | M.J. Driscoll, P. Pickard (Sandia National Laboratories) | 300 MWe Supercritical CO₂ Plant Layout and Design | June | 2004 |
| GFR | 15 | Y. Wang, G.R. Guenette, P. Hejzlar, M.J. Driscoll | M.J. Driscoll, P. Pickard (Sandia National Laboratories) | Supercritical CO₂ Turbine and Compressor Design | June | 2004 |
| GFR | 16 | J. Hejzlar (Arlington High School) | Computer Code for the Analysis of Printed Circuit Heat Exchangers with Zigzag Channels | August | 2004 | |
| GFR | 17 | M.J. Driscoll, P. Hejzlar, N. Carstens, Y. Wang | M.J. Driscoll, P. Pickard (Sandia National Laboratories) | Interim Topical Report - Simulation of Supercritical CO₂ Brayton Cycle Plants | September | 2004 |
| GFR | 21 | M.J. Driscoll, P. Hejzlar | M.J. Driscoll, K. Weaver (Idaho National Laboratory) | An Innovative Gas-Cooled Fast Reactor | September | 2004 |
| GFR | 3 | Y. Wang | Aerodynamic Design of Turbine for S-CO₂ Brayton Cycle | June | 2003 | |
| GFR | 4 | K. Gezelius, V. Dostal, M.J. Driscoll and P. Hejzlar | Design of Shell and Tube Heat Exchanger for the S-CO₂ Cycle and Laminar Flow in Microchannel Heat Exchangers | May | 2003 | |
| GFR | 5 | P. Yarsky | Neutronic Evaluation of GFR Breed and Burn Fuels | May | 2003 | |
| GFR | 7 | J. Plaue and K.R. Czerwinski | Evaluation of Uranium Carbide and Sulfide Fuels for a Gas-Cooled Fast Reactor Utilizing Dry Reprocessing | October | 2003 | |
| GFR | 1 | S. Thon | Selection of Materials for a Supercritical CO₂ Cooled GCFR | August | 2002 | |
| GFR | 2 | J. Eapen | Analysis of a Natural Convection Loop for POST-LOCA GCFR Decay Heat Removal | December | 2002 |
| Program | Type | Number | Revision | Author | Principal Investigator | Title | Month | Year |
|---|---|---|---|---|---|---|---|---|
| MRR | TR | 7 | K.E. Plumer; T.H. Newton; B. Forget, | Estimate of Radiation Release from MIT Reactor with Low Enriched Uranium (LEU) Core During Maximum Hypothetical Accident | June | 2011 | ||
| MRR | TR | 8 | S.A. Kempf; Lwen Hu; B. Forget, | Design and Optimization of a High Thermal Flux Research Reactor via Kriging-Based Algorithm | June | 2011 | ||
| MRR | DES | 9 | M. Bean; G. DeWitt; D. Cabeche; T. Gerrity; G. Haratyk; A. Kersting; Y.H. Lee; G. Lenci; C. Lin; F. Metzler; R. Ochoukov; M. Reed; V. Sobes; R. Sugrue; E. Shwageraus; A. Wisniowska; M. Virgen; P. Youchak, | Conceptual Design of Molten Salt Loop Experiment for MIT Research Reactor | August | 2011 | ||
| MRR | TR | 4 | T.S. Ellis; B. Forget; M.S. Kazimi; T.H. Newton; E.E. Pilat, | Design of a Low Enrichment, Enhanced Fast Flux Core for the MIT Research Reactor | February | 2009 | ||
| MRR | TR | 5 | Y. Wang; Lwen Hu; T.H. Newton; M.S. Kazimi, | Evaluation of the Thermal-Hydraulic Operating Limits of HEU-LEU Transition Cores for the MIT Research Reactor | May | 2009 | ||
| MRR | TR | 6 | P.K. Romano; T.H. Newton; B. Forget, | Developing Fuel Management Capabilities Based on Coupled Monte Carlo Depletion in Support of the MIT Research Reactor Conversion | June | 2009 | ||
| MRR | TR | 2 | Y.C. Ko; Lwen Hu; M.S. Kazimi, | Thermal Hydraulic Analysis of a Low-Enrichment Uranium Core for the MIT Research Reactor | January | 2008 | ||
| MRR | TR | 3 | S.Y-T. Wong; L. Hu; M.S. Kazimi, | Pressure Drop Measurements and Flow Distribution Analysis for MIT Research Reactor with Low-Enriched Fuel | September | 2008 |
| Program | Type | Number | Revision | Author | Principal Investigator | Title | Month | Year |
|---|---|---|---|---|---|---|---|---|
| NES | TR | 7 | M.J. Memmott, M.J. Driscoll, M.S. Kazimi, P. Hejzlar | Hydrogen Production by Steam Electrolysis Using a Super-critical CO₂-Cooled Fast Reactor | February | 2007 | ||
| NES | TR | 9 | A.F. Bersak, A.C. Kadak | Integration of Nuclear Energy with Oil Sands Projects for Reduced Greenhouse Gas Emissions and Naturaly Gas Consumption | August | 2007 | ||
| NES | TR | 6 | B.D. Middleton and M.S. Kazimi | An Alternative to Gasoline: Synthetic Fuels from Nuclear Hydrogen and Captured CO2 | July | 2006 | ||
| NES | TR | 3 | Y.H. Jeong, P. Saha, and M.S. Kazimi | The Attributes of a Nuclear-Assisted Gas Turbine Power Cycle | February | 2005 | ||
| NES | TR | 4 | Y.H. Jeong, M.S. Kazimi, K.J. Hohnholt, and B. Yildiz | Optimization of the Hybrid Sulfur Cycle for Hydrogen Generation | May | 2005 | ||
| NES | DES | 5 | G. Becerra, E. Esparza, A. Finan, E. Helvenston, S. Hembrador, K. Hohnholt, T. Khan, D. Legault, M. Lyttle, K. Miu, C. Murray, N. Parmar, S. Sheppard, C. Sizer, E. Zakszewski, K. Zeller | Nuclear Technology and Canadian Oil Sands: Integration of Nuclear Power and in situ Oil Extraction | December | 2005 | ||
| NES | TR | 2 | B. Yildiz, K. Hohnholt, and M.S. Kazimi | Hydrogen Production Using High Temperature Steam Electrolysis and Gas Reactors with Supercritical CO2 Cycles | December | 2004 | ||
| NES | TR | 1 | B. Yildiz and M.S. Kazimi | Nuclear Energy Options for Hydrogen and Hydrogen-based Liquid Fuels Production | September | 2003 |
| Program | Type | Number | Revision | Author | Principal Investigator | Title | Month | Year |
|---|---|---|---|---|---|---|---|---|
| NFC | 129 | A.J. Mieloszyk | An Improved Structural Mechanics Model for the FRAPCON Nuclear Fuel Performance Code | June | 2012 | |||
| NFC | TR | 113 | B. Sapiie, M. Driscoll, K. Jensen | Regional Examples of Geological Settings for Nuclear Waste Disposal in Deep Boreholes | January | 2010 | ||
| NFC | PR | 114 | L. Zhang, A. Lerch, B. Feng, P. Hejzlar, E. Pilat, M. Kazimi | M. Kazimi, P. Hejzlar | Evaluation of High Power Density Annular Fuel for Korean OPR-1000 Reactor: Final Report | March | 2010 | |
| NFC | TR | 118 | T. Conboy, T. McKrell, M.S. Kazimi | Assessment of Helical-Cruciform Fuel Rods for High Power Density LWRs | May | 2010 | ||
| NFC | PR | 121 | K.G. Jensen, M.J. Driscoll | Plugging of Deep Boreholes for HLW Disposal | July | 2010 | ||
| NFC | TR | 122 | M. Massie, B. Forget | A Generalized Optimization Methodology for Isotope Management | September | 2010 | ||
| NFC | 128 | T. Kwak | Nuclear Non-Proliferation Regime Effectiveness: An Integrated Methodology for Analyzing Highly Enriched Uranium Production Scenarios at Gas Centrifuge Enrichment Plants | February | 2010 | |||
| NFC | TR | 105 | MIT - L. Guerin, B. Feng, P. Hejzlar, B. Forget, M. Kazimi; Argonne Nat'l Lab - L. Van Den Durpel, A. Yacout, T. Taiwo; INL - B. Dixon, G. Matthern; Commissariat a l'Energie Atomique - L. Boucher, M. Delpech, R. Girieud, M. Meyer | A Benchmark Study of Computer Codes for System Analysis of the Nuclear Fuel Cycle | April | 2009 | ||
| NFC | TR | 108 | Y. Du, J. Parsons | Update on the Cost of Nuclear Power | May | 2009 | ||
| NFC | TR | 109 | B. Sapiie, M.J. Driscoll | A Review of Geology-Related Aspects of Deep Borehole Disposal of Nuclear Wastes | August | 2009 | ||
| NFC | TR | 110 | A. Karahan, J. Buongiorno | Modeling of Thermo-Mechanical and Irradiation Behavior of Metallic and Oxide Fuels for Sodium Fast Reactors | August | 2009 | ||
| NFC | TR | 111 | L. Guerin, M. Kazimi | Impact of Alternative Nuclear Fuel Cycle Options on Infrastructure and Fuel Requirements, Actinide and Waste Inventories, and Economics | September | 2009 | ||
| NFC | TR | 99 | Y-C. Ko, L-W. Hu, M. Kazimi | Thermal Hydraulic Analysis of a Low Enrichment Uranium Core for the MIT Research Reactor | January | 2008 | ||
| NFC | TR | 100 | B. Feng, P. Hejzlar, M. Kazimi | On the Use of High Performance Annular Fuel in PWRs | June | 2008 | ||
| NFC | PR | 101 | N. Todreas, P. Hejzlar, C. Fong, A. Nikiforova, R. Petroski, E. Shwageraus, J. Whitman | N. Todreas, P. Hejzlar | Flexible Conversion Ratio Fast Reactor Systems Evaluation Final Report | June | 2008 | |
| NFC | PR | 102 | M. Kazimi, T. Conboy, R. Hu, A. Karahan, J. Buongiorno, P. Hejzlar, T. McKrell, Y. Kimura | M. Kazimi | Core Design Options for High Power Density BWRs | September | 2008 | |
| NFC | TR | 104 | Z. Xu, P. Hejzlar | MCODE, Version 2.2: An MCNP-ORIGEN Depletion Program | December | 2008 | ||
| NFC | TR | 92 | A. Karahan, J. Buongiorno, M. Kazimi | An Evolutionary Fuel Assembly Design for High Power Density BWRs | July | 2007 | ||
| NFC | TR | 93 | T. Conboy, P. Hejzlar, M. Kazimi | Thermal-Hydraulic Analysis of Cross-Shaped Spiral Fuel in High Power Density BWRs | July | 2007 | ||
| NFC | TR | 94 | N. Bonnet, M. Kazimi | Sensitivity of Economic Performance of the Nuclear Fuel Cycle to Simulation Modeling Assumptions | July | 2007 | ||
| NFC | TR | 95 | J. Beccherle, P. Hejzlar, M. Kazimi | PWR Transition to a Higher Power Core Using Annular Fuel | September | 2007 | ||
| NFC | PR | 97 | M. Kazimi, J. Buongiorno, T. Conboy, T. Ellis, P. Ferroni, P. Hejzlar, S-P. Kao, A. Karahan, T. McKrell, E. Pilat, N. Todreas | M. Kazimi | Core Design Options for High Power Density BWRs | November | 2007 | |
| NFC | TR | 98 | D. Carpenter, K. Ahn, S. Kao, P. Hejzlar, M. Kazimi | Assessment of Silicon Carbide Cladding for High Performance Light Water Reactors | November | 2007 | ||
| NFC | TR | 77 | C. Shuffler, J. Trant, N. Todreas, and A. Romano | Thermal Hydraulic and Economic Analysis of Grid-Supported, Hydride-Fueled PWRs | January | 2006 | ||
| NFC | TR | 78 | P.R. Diller and N.E. Todreas | Wire Wrapped Fuel Pin Hexagonal Arrays for PWR Service | January | 2006 | ||
| NFC | PR | 79 | P. Ferroni and N.E. Todreas | Steady State Thermal Hydraulic Analysis of Hydride Fueled BWRs | May | 2006 | ||
| NFC | PR | 79 | P. Ferroni and N.E. Todreas | Thermal Hydraulic Analysis of Hydride-Fueled BWRs | February | 2006 | ||
| NFC | PR | 82 | M.S. Kazimi, P. Hejzlar et al. | High Performance Fuel Design For Next Generation PWRs: Final Report | January | 2006 | ||
| NFC | TR | 83 | T.H. Newton, M.S. Kazimi, and E. Pilat, et al. | Development of a Low Enrichment Uranium Core for the MIT Reactor | March | 2006 | ||
| NFC | TR | 84 | H. Ham and M.W. Golay | An Integrated Methodology for Quantitative Assessment of Proliferation Resistance of Advanced Nuclear Systems Using Probabilistic Methods | May | 2006 | ||
| NFC | TR | 85 | M. Visosky, M.S. Kazimi and P. Hejzlar | Actinide Minimization Using Pressurized Water Reactors | June | 2006 | ||
| NFC | TR | 86 | A. Aquien, M.S. Kazimi and P. Hejzlar | Fuel Cycle Options for Optimized Recycling of Nuclear Fuel | June | 2006 | ||
| NFC | PR | 87 | N.E. Todreas, P. Hejzlar | Flexible Conversion Ratio Reactor Systems Evaluation: 1st Quarterly Report | June | 2006 | ||
| NFC | TR | 88 | Y. Shatilla, P. Hejzlar, and M.S. Kazimi | A PWR Self-Contained Actinide Transmutation System | September | 2006 | ||
| NFC | PR | 89 | M. Kazimi, J. Buongiorno, T. Conboy, T. Ellis, P. Ferroni, P. Hejzlar, S-P. Kao, A. Karahan, K. Kobayashi, E. Pilat, N. Todreas | M. Kazimi | Core Design Options for High Power Density BWRs | December | 2006 | |
| NFC | TR | 70 | Rev. 1 | T. Boscher, P. Hejzlar, M.S. Kazimi, N.E. Todreas, and A. Romano | Alternative Fuel Cycle Strategies for Nuclear Power Generation in the 21st Century. Revision 1 | June | 2005 | |
| NFC | PR | 72 | M.S. Kazimi, P. Hejzlar et al. | High Performance Fuel Design for Next Generation PWRs, 13th Quarterly Report | January | 2005 | ||
| NFC | PR | 73 | M.S. Kazimi, P. Hejzlar et al. | High Performance Fuel Design for Next Generation PWRs, 14th Quarterly Report | April | 2005 | ||
| NFC | PR | 74 | M.S. Kazimi, P. Hejzlar et al. | High Performance Fuel Design for Next Generation PWRs, 15th Quarterly Report | August | 2005 | ||
| NFC | TR | 75 | D. Feng, M.S. Kazimi, and P. Hejzlar | Innovative Fuel Designs for High Power Density Pressurized Water Reactor | September | 2005 | ||
| NFC | PR | 76 | M.S. Kazimi, P. Hejzlar et al. | High Performance Fuel Design For Next Generation PWRs: 4th Annual Report | October | 2005 | ||
| NFC | TR | 80 | H. Feinroth and Y. Yuan | Feasibility of Partial ZrO2 Coatings on the Outer Surface of Annular UO2 Pellets to Control Gap Conductance | June | 2005 | ||
| NFC | TR | 81 | D. Carpenter and G. Kohse | Experimental Determination of the Thermal Conductivity of a Lead Bismuth, Eutectic-Filled Annulus | June | 2005 | ||
| NFC | PR | 61 | M.S. Kazimi, P. Hejzlar et al. | M.S. Kazimi, P. Hejzlar | High Performance Fuel Design for Next Generation PWRs, 9th Quarterly Report | January | 2004 | |
| NFC | PR | 62 | M.S. Kazimi, P. Hejzlar et al. | High Performance Fuel Design for Next Generation PWRs, 10th Quarterly Report | April | 2004 | ||
| NFC | TR | 62 | J.A. Malen, N.E. Todreas, A. Romano | Thermal Hydraulic Design of Hydride Fueled PWR Cores | March | 2004 | ||
| NFC | TR | 63 | Xu, Y. Otsuka, P. Hejzlar, M.J. Driscoll, and M.S. Kazimi | Neutronic Design of PWR Cores with High Performance Annular Fuel | May | 2004 | ||
| NFC | TR | 64 | Y. Inoue, Z. Xu, E. Pilat, and M.S. Kazimi | Combining Thorium with Burnable Poison for Reactivity Control of a Very Long Cycle BWR | June | 2004 | ||
| NFC | TR | 65 | M. Todosow and M. Kazimi | Optimization of Heterogeneous Utilization of Thorium in PWRs to Enhance Proliferation Resistance and Reduce Waste | July | 2004 | ||
| NFC | PR | 66 | M.S. Kazimi, P. Hejzlar et al. | M.S. Kazimi, P. Hejzlar | High Performance Fuel Design for Next Generation PWRs, 11th Quarterly Report | July | 2004 | |
| NFC | TR | 67 | Y. Yuan, M.S. Kazimi, and P. Hejzlar | The Design of High Power Density Annular Fuel for LWRs | September | 2004 | ||
| NFC | PR | 68 | M.S. Kazimi, P. Hejzlar et al. | High Performance Fuel Design for Next Generation PWRs, 3rd Annual Report | October | 2004 | ||
| NFC | PR | 68 | Part II | M.S. Kazimi, P. Hejzlar et al. | M.S. Kazimi, P. Hejzlar | High Performance Fuel Design for Next Generation PWRs, 3rd Annual Report Appendices | October | 2004 |
| NFC | TR | 69 | T. Boscher, A. Romano, P. Hejzlar, M.S. Kazimi, and N.E. Todreas | The CAFCA Code for Simulation of Nuclear Fuel Cycles: Description of Methodology, Assumptions, and Initial Results | December | 2004 | ||
| NFC | TR | 70 | T. Boscher, P. Hejzlar, M.S. Kazimi, N.E. Todreas, and A. Romano | Alternative Fuel Cycle Strategies for Nuclear Power Generation in the 21st Century | December | 2004 | ||
| NFC | PR | 71 | P. Morra, Z. Xu, P. Hejzlar, P. Saha, and M.S. Kazimi | Neutronic and Thermal Hydraulic Designs of Annular Fuel for High Power Density BWRs | December | 2004 | ||
| NFC | TR | 52 | G. Kohse, P. Hejzlar, T. Newton, E.E. Pilat, W.Y. Kato, and M.S. Kazimi | Safety Evaluation Report for Irradiation of Annular Fuel in the MITR-II | January | 2003 | ||
| NFC | TR | 53 | Z. Xu, M.J. Driscoll, and M.S. Kazimi | Design Strategies for Optimizing High Burnup Fuel in Pressurized Water Reactors | July | 2003 | ||
| NFC | PR | 54 | M.S. Kazimi et al. | High Performance Fuel Design for Next Generation PWRs, 6th Quarterly Report | March | 2003 | ||
| NFC | TR | 55 | Y. Long, Y. Zhang, and M.S. Kazimi | Inert Matrix Materials as Hosts of Actinide Nuclear Fuels | March | 2003 | ||
| NFC | PR | 56 | M.S. Kazimi et al. | High Performance Fuel Design for Next Generation PWRs, 7th Quarterly Report | May | 2003 | ||
| NFC | TR | 57 | D. Wang, M.S. Kazimi, and M.J. Driscoll | Optimization of a Heterogeneous Thorium-Uranium Core Design for Pressurized Water Reactors | July | 2003 | ||
| NFC | PR | 58 | M.S. Kazimi et al. | High Performance Fuel Design for Next Generation PWRs, 2nd Annual Report | August | 2003 | ||
| NFC | TR | 59 | A. Romano, P. Hejzlar, and N.E. Todreas | Optimization of Actinide Transmutation in Innovative Lead-Cooled Fast Reactors | October | 2003 | ||
| NFC | PR | 60 | E. Shwageraus, P. Hejzlar and M.S. Kazimi | Optimization of the LWR Nuclear Fuel Cycle for Minimum Waste Production | October | 2003 | ||
| NFC | TR | 61 | E. Parent, N.E. Todreas, and M.J. Driscoll | Nuclear Fuel Cycles for Mid-century Deployment | December | 2003 | ||
| NFC | TR | 36 | Y. Sevestre and K.R. Czerwinski | Characterization of Zirconia Based Thoria-Urania Ceramics for Nuclear Fuel and Waste Applications | January | 2002 | ||
| NFC | TR | 38 | H.T. Kim, H.C. No, P. Hejzlar, and M.S. Kazimi | Safety Analysis of the Annular Fuel by RELAP5/MOD3.2 | January | 2002 | ||
| NFC | PR | 40 | M.S. Kazimi et al. | High Performance Fuel Design for Next Generation PWRs, 2nd Quarterly Report | February | 2002 | ||
| NFC | PR | 41 | M.S. Kazimi et al. | High Performance Fuel Design for Next Generation PWRs, 3rd Quarterly Report | May | 2002 | ||
| NFC | TR | 42 | D.S. Sentell, Jr., M.W. Golay, and M.J. Driscoll | A Quantitative Assessment of Nuclear Weapons Proliferation Risk Utilizing Probabilistic Methods | May | 2002 | ||
| NFC | TR | 43 | D.K. Thompson, K.F. Hansen, and M.S. Kazimi | The Effects of Societal Concerns on the Energy Power Industry | May | 2002 | ||
| NFC | TR | 44 | Y. Long, M.S. Kazimi, R.G. Ballinger, and J.E. Meyer | Modeling the Performance of High Burnup Thoria and Urania PWR Fuel | July | 2002 | ||
| NFC | TR | 45 | M. Laughter, P. Hejzlar, and M.S. Kazimi | Self-Protection Characteristics of Uranium-233 in the ThO2 -UO2 PWR Fuel Cycle | July | 2002 | ||
| NFC | TR | 46 | E. Shwageraus, X. Zhao, P. Hejzlar, M.J. Driscoll, and M.S. Kazimi | Optimization of Micro-Heterogeneous Uranium-Thorium Dioxide PWR Fuels for Economics and Enhanced Proliferation Resistance | July | 2002 | ||
| NFC | TR | 47 | J.G.B. Saccheri and N.E. Todreas | Core Design Strategy for Long-Life, Epithermal, Water-Cooled Reactors | July | 2002 | ||
| NFC | PR | 48 | M.S. Kazimi et al. | High Performance Fuel Design for Next Generation PWRs, 1st Annual Report | August | 2002 | ||
| NFC | TR | 49 | E. Schwageraus, Y. Zhang, P. Hejzlar, and M.S. Kazimi | Transmutation of Actinides in PWRs Using Fertile Free Fuels | October | 2002 | ||
| NFC | TR | 50 | A. Romano, P. Hejzlar, and N.E. Todreas | Dedicated Fast Reactors for Efficient Minor Actinides Incineration: Neutronic Design of a Pb-Bi Cooled Concept | October | 2002 | ||
| NFC | PR | 51 | M.S. Kazimi, P. Hejzlar, R. Ballinger, M. Driscoll, E. Pilat, D. Feng, G. Kohse, Y. Otsuka, Z. Xu, Y. Yuan, J. Zhang, P. Stahl, D. Carpenter | M.S. Kazimi | High Performance Fuel Design for Next Generation PWRs, 5th Quarterly Report | November | 2002 | |
| NFC | PR | 1 | M.S. Kazimi, P. Hejzlar, R. Ballinger, M. Driscoll, G. Kohse, Z. Xu, Y. Yuan | M.S. Kazimi | High Performance Fuel Design for Next Generation PWRs | November | 2001 | |
| NFC | TR | 28 | Z. Xu, M.J. Driscoll, and M.S. Kazimi | Systematic Study of Moderation Effects on UO2 Fueled Lattices | May | 2001 | ||
| NFC | TR | 29 | S.M. Oggianu, M.S. Kazimi, and H.C. No | High Burnup Fuels for Advanced Nuclear Reactors | May | 2001 | ||
| NFC | TR | 30 | R. Sobeski, K.F. Hansen, and M.S. Kazimi | Modeling the Dynamic Complexity of the Nuclear Energy Policymaking Process: The Nuclear Proliferation Issue | June | 2001 | ||
| NFC | TR | 31 | X. Zhao, M.J. Driscoll, and M.S. Kazimi | Micro-Heterogeneous Thorium Based Fuel Concepts for Pressurized Water Reactors | August | 2001 | ||
| NFC | TR | 32 | F.A. Felder and K.F. Hansen | The U.S. Nuclear Power Industry and Electric Industry Restructuring | July | 2001 | ||
| NFC | TR | 33 | S.M. Oggianu, K.F. Hansen, and M.S. Kazimi | Modeling the Dynamic Complexity of the Nuclear Policymaking Process and System: The High Level Nuclear Waste Issue | August | 2001 | ||
| NFC | TR | 34 | C.A. McDonald and K.F. Hansen | Modeling the U.S. Electric Energy Social-Political Environment: A Global Warming-Nuclear Power Policymaking Construct | August | 2001 | ||
| NFC | TR | 35 | V.L. Curran and K.R. Czerwinski | Thorium Oxide Dissolution Kinetics for Hydroxide and Carbonate Complexation | August | 2001 | ||
| NFC | TR | 37 | Y. Yuan, H.C. No, and M.S. Kazimi | A Preliminary Investigation of Performance of Rock-Like Fuel For High Burnup in LWRs | December | 2001 | ||
| NFC | PR | 39 | M.S. Kazimi et al. | High Performance Fuel Design for Next Generation PWRs, 1st Quarterly Report | November | 2001 | ||
| NFC | TR | 19 | D. Kim, M.S. Kazimi, N.E. Todreas, and M.J. Driscoll | Economic Analysis of the Fuel Cycle of Actinide Burning Systems | February | 2000 | ||
| NFC | TR | 21 | S.M. Oggianu and M.S. Kazimi | A Review of Properties of Advanced Nuclear Fuels | February | 2000 | ||
| NFC | TR | 22 | Y. Yuan, P. Monnier, C.S. Rim, and M.S. Kazimi | Fission Gas Release for Thoria-Urania Fuels: A Preliminary Investigation | September | 2000 | ||
| NFC | TR | 23 | P.E. Owen and K.R. Czerwinski | Waste Characteristics of Spent Nuclear Fuel From a Pebble Bed Reactor | June | 2000 | ||
| NFC | TR | 24 | M.S. Kazimi, M.J. Driscoll, R.G. Ballinger, V.L. Curran, K.R. Czerwinski, Y. Long, H.C. No, S.M. Oggianu, X. Zhao | Advanced Fuel for High Burnup and Proliferation Resistance in Light Water Reactors: Annual Report | July | 2000 | ||
| NFC | TR | 24 | Rev. 1 | M.S. Kazimi, M.J. Driscoll, R.G. Ballinger, V.L. Curran, K.R. Czerwinski, Y. Long, H.C. No, S.M. Oggianu, X. Zhao | Advanced Fuel for High Burnup and Proliferation Resistance in Light Water Reactors: Annual Report, Rev. 1 | July | 2000 | |
| NFC | TR | 25 | M. Busse and M.S. Kazimi | Thermal and Economic Analysis of Thorium-Based Seed-Blanket Fuel Cycles for Nuclear Power Plants | August | 2000 | ||
| NFC | TR | 26 | D. Wang, M.J. Driscoll, and M.S. Kazimi | Design and Performance Assessment of a PWR Whole-Assembly Seed and Blanket Thorium-Based Fuel Cycle | October | 2000 | ||
| NFC | TR | 27 | X. Zhao, P. Hejzlar, and M.J. Driscoll | Comparison of Code Results for PWR Thorium/Uranium Pin Cell Burnup | November | 2000 | ||
| NFC | TR | 16 | M.S. Kazimi, K.R. Czerwinski, M.J. Driscoll, P. Hejzlar, and J.E. Meyer | On the Use of Thorium in Light Water Reactors | April | 1999 | ||
| NFC | TR | 17 | T. Tatsuro, S.R. Connors, and M.S. Kazimi | The Role of Nuclear Energy in Southeast Asia | June | 1999 | ||
| NFC | TR | 18 | M.S. Kazimi, M.J. Driscoll, R.G. Ballinger et al. | Proliferation Resistant, Low Cost, Thoria-Urania Fuel for Light Water Reactors | July | 1999 | ||
| NFC | TR | 20 | X. Zhao, D. Wang, Z. Xu, M.J. Driscoll, and M.S. Kazimi | A Preliminary Analysis of the Effect of Seed and Blanket Heterogeneity on PWR Core Neutronics | December | 1999 | ||
| NFC | TR | 7 | C.S. Handwerk, M.J. Driscoll, N.E. Todreas, and M.V. McMahon | Economic Analysis of Extended Operating Cycles in Existing LWRs | January | 1998 | ||
| NFC | TR | 8 | C.S. Handwerk, N.E. Todreas, J.E. Meyer, and M.J. Driscoll | Fuel Performance Aspects of Extended Operating Cycles in Existing LWRs | January | 1998 | ||
| NFC | TR | 9 | H.J. MacLean, M.V. McMahon, and M.J. Driscoll | Uranium and Separative Work Utilization in Light Water Reactors | January | 1998 | ||
| NFC | TR | 10 | D.L. Brodeur, V.T. Angus, and N.E. Todreas | Optimization of Nuclear Power Utility Performance | July | 1998 | ||
| NFC | TR | 11 | L. Garcia-Delgado and N.E. Todreas | Improvement in Nuclear Plant Capacity Factors Through Longer Cycle Length Operation: Final Report | July | 1998 | ||
| NFC | TR | 12 | C.S. Handwerk, M.J. Driscoll, and N.E. Todreas | A User's Guide for MUSCLE (MIT Utility Study on Cycle Length Economics | April | 1998 | ||
| NFC | TR | 13 | L. Garcia-Delgado, M.J. Driscoll, J.E. Meyer, and N.E. Todreas | Design of Economically Optimum PWR Reload Core for a 36-Month Cycle | May | 1998 | ||
| NFC | TR | 14 | C.A. Bollman, M.J. Driscoll, and M.S. Kazimi | Environmental and Economic Performance of Direct Use of Spent PWR Fuel in CANDU Reactors | June | 1998 | ||
| NFC | TR | 15 | P. Hejzlar, N.E. Todreas, M.J. Driscoll, and Y. Long | Assessment of New Technologies for Selected Next Generation Light Water Reactors: Final Report | October | 1998 | ||
| NFC | TR | 1 | P. Chodak, M.J. Driscoll, M.M. Miller, and N.E. Todreas | Destruction of Plutonium Using Non-Uranium Fuels in Pressurized Water Reactor Peripheral Assemblies | January | 1997 | ||
| NFC | TR | 2 | F. Morosan and M.S. Kazimi | Multi-attribute Analysis of Alternatives for Hanford Tanks Remediation System | January | 1997 | ||
| NFC | TR | 3 | D.L. Brodeur, N.E. Todreas | Improvement in Nuclear Plant Capacity Factors Through Longer Cycle Length Operation: Annual Report | July | 1997 | ||
| NFC | TR | 4 | M.V. McMahon, C.S. Handwerk, H.J. MacLean, M.J. Driscoll, and N.E. Todreas | Modeling and Design of Reload LWR Cores for an Ultra-Long Operating Cycle, Rev. 1 | July | 1997 | ||
| NFC | TR | 4 | Rev. 1 | M.V. McMahon, C.S. Handwerk, H.J. MacLean, M.J. Driscoll, and N.E. Todreas | Modeling and Design of Reload LWR Cores for an Ultra-Long Operating Cycle, Rev. 1 | September | 1997 | |
| NFC | TR | 5 | K.W. Wenzel | Photonuclear Reaction for Simulated Radiation Damage in Nuclear Waste Forms | September | 1997 | ||
| NFC | TR | 6 | K.W. Budlong Sylvester, S.A. Simonson, K.W. Wenzel, and M.J. Driscoll | Weapons-Grade Plutonium Disposition: An Alternate Immobilization Strategy | June | 1997 |
| Program | Type | Number | Revision | Author | Principal Investigator | Title | Month | Year |
|---|---|---|---|---|---|---|---|---|
| NSA | TR | 1 | V. Dostal, K. Gezelius, J. Horng, J. Koser, J.P. IV, E. Shwageraus, P. Yarsky, and A.C. Kadak | Mission to Mars: How to Get People There and Back with Nuclear Energy | September | 2004 | ||
| NSA | TR | 2 | P. Yarsky, A.C. Kadak, and M.J. Driscoll | Design of a Sodium-cooled Epithermal Long-term Exploration Nuclear Engine | September | 2004 | ||
| NSA | DES | 3 | A. Bushman, D.M. Carpenter, T.S. Ellis, S.P. Gallagher, M.D. Hershcovitch, M.C. Hine, E.D. Johnson, S.C. Kane, M.R. Presley, A.H. Roach, S. Shaikh, M.P. Short, and M.A. Stawicki | The Martian Surface Reactor: An Advanced Nuclear Power Station for Manned Extraterrestrial Exploration | December | 2004 |
| Program | Type | Number | Revision | Author | Principal Investigator | Title | Month | Year |
|---|---|---|---|---|---|---|---|---|
| NSP | TR | 34 | Williams, A., and Golay, M.W. | Evaluating the ‘model’ for consent-based siting: Stakeholder Acceptance and the Waste Isolation Pilot Plant | 2016 | |||
| NSP | TR | 35 | Williams, A., and Golay, M.W. | The Curious Case of the Marcellus Shale: PA vs. NY Fracking Case Study Summary | 2016 | |||
| NSP | TR | 36 | Williams, A., and Golay, M.W. | Stakeholder Engagement Strategy Development Framework for Socially Controversial Projects | 2016 | |||
| NSP | TR | 33 | Laws, A., Hale, P. and Golay, M.W. | Models for Stakeholder Relationship Management at Socially Controversial Facilities | 2015 | |||
| NSP | TR | 32 | Guyer, B. L. and Golay, M. | Nuclear Power Plant Performance Assessment Pertaining to Plant Aging in France and the United States | 2014 | |||
| NSP | TR | 25 | J. Buongiorno, R. Ballinger, M. Driscoll, B. Forget, C. Forsberg, M. Golay, M. Kazimi, N. Todreas, J. Yanch | Technical Lessons Learned from the Fukushima-Daichii Accident and Possible Corrective Actions for the Nuclear Industry: An Initial Evaluation | May | 2011 | ||
| NSP | TR | 25 | Rev. 1 | J. Buongiorno, R. Ballinger, M. Driscoll, B. Forget, C. Forsberg, M. Golay, M. Kazimi, N. Todreas, J. Yanch | Technical Lessons Learned from the Fukushima-Daichii Accident and Possible Corrective Actions for the Nuclear Industry: An Initial Evaluation | July | 2011 | |
| NSP | TR | 26 | Gibbs, J. P., R. G. Ballinger, and J. Jackson, | Stress Corrosion Cracking and Crack Tip Characterization of Alloy X-750 in Light Water Reactor Environments | September | 2011 | ||
| NSP | TR | 27 | Lucas, T. R., and R. G. Ballinger, | The Effect of Thermal Aging and Boiling Water Reactor Environment on Type 316L Stainless Steel Welds | September | 2011 | ||
| NSP | TR | 28 | Johnson, B. C., and G. E. Apostolakis, | Application of the Technology Neutral Framework to Sodium-Cooled Fast Reactors | October | 2011 | ||
| NSP | TR | 29 | Cavalieri d’Oro, E., and M. W. Golay, | A Unified Risk-‐informed Framework to Assess the Proliferation Risk and License the Proliferation Performance of Nuclear Energy Systems | September | 2011 | ||
| NSP | PR | 30 | G. Apostolakis, M. Driscoll, M. Golay, A. Kadak, N. Todreas, T. Aldemir, R. Denning, and M. Lineberry, | Executive Summary: Investigation of Risk-‐Informed Methodologies to Improve Sodium-‐Cooled Fast Reactor Economics With Safety and Non-‐Proliferation Constraints | October | 2011 | ||
| NSP | PR | 31 | MIT - G. Apostolakis, M. Driscoll, M. Golay, A. Kadak, and N. Todreas The Ohio State Univ. - T. Aldemir and R. Denning Idaho State Univ. - M. Lineberry |
Investigation of Risk-Informed Methodologies to Improve Sodium-Cooled Fast Reactor Economics with Safety and Non-Proliferation Constraints | October | 2011 | ||
| NSP | TR | 24 | D.R. Langewisch | Uncertainty and Sensitivity Analysis for Long-Running Computer Codes: A Critical Review | January | 2010 | ||
| NSP | TR | 23 | L. Debesse, G.E. Apostolakis, M.J. Driscoll | The Use of Frequency-Consequence Curves in Future Reactor Licensing | January | 2007 | ||
| NSP | TR | 21 | B. Yildiz and M.W. Golay | Development of a Hybrid Intelligent System for On-line, Real-time Monitoring of Nuclear Power Plant Operations | April | 2006 | ||
| NSP | TR | 22 | N.J. Haschka and N.E. Todreas | Improving Nuclear Power Plant Performance: An Assessment of the US Nuclear Fleet Outage Performance (1990-2005) | July | 2006 | ||
| NSP | PR | 19 | A.C. Kadak and T. Matsuo | The Nuclear Industry's Transition to Risk Informed Regulation and Operation in the United States | August | 2005 | ||
| NSP | TR | 20 | B.D. Middleton and M.W. Golay | Use of Information Theory Techniques with System Dynamics Models | November | 2005 | ||
| NSP | TR | 18 | A.C. Kadak, Y. Sakuragi, M.A. Stawicki, K.F. Hansen | Quantitative Performance Comparison of Japanese and American Nuclear Power Industries | January | 2004 | ||
| NSP | PR | 17 | L.-W. Hu, J. Lee, P. Saha, M.S. Kazimi | Thermal Striping in LWR Piping Systems | December | 2003 | ||
| NSP | TR | 8 | S.M. Oggianu and K.F. Hansen | Modeling the Dynamic Complexity of the Energy Policymaking Process | March | 2002 | ||
| NSP | TR | 9 | S.M. Oggianu and K.F. Hansen | Modeling of Electric Energy Policymaking | March | 2002 | ||
| NSP | TR | 10 | A.W. Sause and S.M. Oggianu | Modeling Energy Policy Making Process as a Response to Social Concern | August | 2002 | ||
| NSP | TR | 11 | S.M. Oggianu and K.F. Hansen | A System Dynamics Model of the Energy Policymaking Process | August | 2002 | ||
| NSP | TR | 12 | M.E. Silsdorf and M.W. Golay | On the Use of Multi-Attribute Utility Theory to Quantify the Desirability of Hydraulic Control Unit Maintenance of a Boiling Water Reactor | August | 2002 | ||
| NSP | TR | 13 | T. Bannai and M.W. Golay | Probabilistic Risk Analysis of Falsification Cases in the Japanese Nuclear Industry | August | 2002 | ||
| NSP | PR | 14 | L-W Hu, M.S. Kazimi, A. Sonin | Thermal Striping in LWR Piping Systems Progress Report: September 2001 through August 2002 | August | 2002 | ||
| NSP | PR | 14 | Rev. 1 | L-W Hu, M.S. Kazimi, A. Sonin | Thermal Striping in LWR Piping Systems Progress Report: September 2001 through August 2002 | August | 2002 | |
| NSP | TR | 15 | D. Kim and M.W. Golay | Bayesian Belief Network (BBN)-Based Advisory System Development for Steam Generator Replacement Project Management | November | 2002 | ||
| NSP | TR | 16 | G.E. Apostolakis, M.W. Golay, J.P. Koser, A. Knight, G. Sato, M.E. Silsdorf | Enhancing the Competitiveness of Nuclear Power Plants through Risk Informed Decision Making | November | 2002 | ||
| NSP | TR | 1 | R. Weil and G.E. Apostolakis | Analysis and Utilization of Operating Experience for Organizational Learning | June | 2001 | ||
| NSP | TR | 2 | K. Marchinkowski, R. Weil, and G.E. Apostolakis | CATILaC: ComputeR Aided Techniques for Identifying Latent Conditions | April | 2001 | ||
| NSP | TR | 3 | B.C. Beer, G.E. Apostolakis, and M.W. Golay | Feasibility Investigations for Risk-Based Nuclear Safety Regulation | February | 2001 | ||
| NSP | TR | 4 | M.R. Galvin and N.E. Todreas | Maintenance Cycle Extension in Advanced Light Water Design | October | 2001 | ||
| NSP | TR | 5 | J.J. Kim, M.W. Golay, G.R. Toro, and O. Afolayan-Jejeloye | Analysis of Direct Seismic Risks and Its Effects on Existing Emergency Response Plans Near a Nuclear Power Station | October | 2001 | ||
| NSP | TR | 6 | Y. Sui, M.W. Golay, and K.F. Hansen | Identification of Performance Indicators for Nuclear Power Plants | September | 2001 | ||
| NSP | TR | 7 | L.W. Hu, K. Nagasawa, P. Hejzlar, and M.S. Kazimi | Thermal Striping in LWR Piping Systems | August | 2001 |