Center for Advanced Nuclear Energy Systems Reports

Published: January 2018

A full listing of reports is below. To request a report, please contact Carolyn Carrington at the Center for Advanced Nuclear Energy Systems.

Programs

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

ANP

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

GFR

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

MRR

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

NES

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

NFC

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

NSA

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

NSP

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