Publications
Nuclear Fuel Cycle (NFC) Technology and Policy Program
| Abstract | MIT-NFC-TR-112 | Guillaume De Roo, John E. Parsons and Benoit Forget, Economics of Nuclear Fuel Cycles: Option Valuation and Neutronics Simulation of Mixed Oxide Fuels (December 2009). |
| Abstract | MIT-NFC-TR-111 | Laurent Guérin and Mujid S. Kazimi, Impact of Alternative Nuclear Fuel Cycle Options on Infrastructure and Fuel Requirements, Actinide and Waste Inventories, and Economics (September 2009). |
| Abstract | MIT-NFC-TR-110 | Aydın Karahan and Jacopo Buongiorno, Modeling of Thermo-Mechanical and Irradiation Behavior of Metallic and Oxide Fuels for Sodium Fast Reactors (August 2009). |
| Abstract | MIT-NFC-TR-109 | B. Sapiie and M. J. Driscoll, A Review of Geology-Related Aspects of Deep Borehole Disposal of Nuclear Waste (August 2009). |
| Abstract | MIT-NFC-TR-108 | Yangbo Du and John E. Parsons, Update on the Cost of Nuclear Power (May 2009). |
| Abstract | MIT-NFC-TR-107 | A. Karahan, J. Buongiorno, and M.S. Kazimi, Modeling the Steady-state Behavior of Metal Fuels in Liquid-Metal Fast Reactors (April 2009) |
| Abstract | MIT-NFC-TR-106 | M.S. Kazimi et al., Core Design Options for High Power Density BWRs. Final Report for Phase Two of a TEPCO Research Project (March 2009). |
| Abstract | MIT-NFC-TR-105 | L. Guerin et al., A Benchmark Study of Computer Codes for System Analysis of the Nuclear Fuel Cycle (April 2009). |
| Abstract | MIT-NFC-TR-104 | Xu and P. Hejzlar, MCODE, Version 2.2: An MCNP-ORIGEN DEpletion Program (December 2008). |
| Abstract | MIT-NFC-TR-103 | Rodney Busquim e Silva, Mujid S. Kazimi, and Pavel Hejzlar, A System Dynamics Study of the Nuclear Fuel Cycle with Recycling: Options and Outcomes for the US and Brazil (November 2008). |
| Abstract | MIT-NFC-PR-102 | Mujid S. Kazimi, Pavel Hejzlar, Jacopo Buongiorno, Thomas Conboy, Rui Hu, Aydin Karahan, and Thomas McKrell, Core Design Options for High Power Density BWRs: Third Annual TEPCO Report (September 2008). |
| Abstract | MIT-NFC-PR-101 | Neil Todreas and Pavel Hejzlar, Flexible Conversion Ratio Fast Reactor Systems Evaluation (Final Report) (June 2008). |
| Abstract | MIT-NFC-TR-100 | Bo Feng, Pavel Hejzlar and Mujid S. Kazimi, On the Use of High Performance Annular Fuel in PWRs (June 2008). |
| Abstract | MIT-NFC-TR-099 | Yu-Chih Ko, Lin-Wen Hu, and Mujid S. Kazimi, Thermal Hydraulic Analysis of a Low Enrichment Uranium Core for the MIT Research Reactor (January 2008). |
| Abstract | MIT-NFC-TR-098 | D. Carpenter, K. Ahn, S. Kao, P. Hejzlar, and M.S. Kazimi, Assessment of Silicon Carbide Cladding for High Performance Light Water Reactors (November 2007). |
| Abstract | MIT-NFC-PR-097 | M.S. Kazimi et al., Core Design Options for High Power Density BWRs (November 2007). |
| Abstract | MIT-NFC-TR-096 | Wenfeng Liu and Mujid S. Kazimi, Modeling of High-Burnup LWR Fuel Response to Reactivity-Initiated Accidents (October 2007). |
| Abstract | MIT-NFC-TR-095 | J. Beccherle, P. Hejzlar, and M.S. Kazimi, PWR Transition to a Higher Power Core Using Annular Fuel (September 2007). |
| Abstract | MIT-NFC-TR-094 | N. Bonnet and M.S. Kazimi, Sensitivity of Economic Performance of the Nuclear Fuel Cycle to Simulation Modeling Assumptions (July 2007). |
| Abstract | MIT-NFC-TR-093 | T.M. Conboy, P. Hejzlar, and M.S. Kazimi, Thermal-Hydraulic Analysis of Cross-Shaped Spiral Fuel in High Power Density BWRs (July 2007). |
| Abstract | MIT-NFC-TR-092 | A. Karahan, J. Buongiorno, and M.S. Kazimi, An Evolutionary Fuel Assembly Design For High Power Density BWRS (July 2007). |
| Abstract | MIT-NFC-TR-091 | N.E. Todreas and P. Hejzlar, Flexible Conversion Ratio Reactor Systems Evaluation: 4th Quarterly Report (April 2007). |
| Abstract | MIT-NFC-TR-090 | N.E. Todreas and P. Hejzlar, Flexible Conversion Ratio Reactor Systems Evaluation: 3rd Quarterly Report (January 2007). |
| Abstract | MIT-NFC-PR-089 | M. S. Kazimi, J. Buongiorno, T. Conboy, T. Ellis, P. Ferroni, P. Hejzlar, S-P. Kao, A. Karahan, K. Kobayashi, E. Pilat, N.E. Todreas, Core Design Options for High Power Density BWRs (December 2006). |
| Abstract | MIT-NFC-TR-088 | Y. Shatilla, P. Hejzlar, and M.S. Kazimi, A PWR Self-Contained Actinide Transmutation System (September 2006). |
| Abstract | MIT-NFC-TR-087 | N.E. Todreas and P. Hejzlar, Flexible Conversion Ratio Reactor Systems Evaluation: 1st Quarterly Report (June 2006). |
| Abstract | MIT-NFC-TR-086 | A. Aquien, M.S. Kazimi and P. Hejzlar, Fuel Cycle Options for Optimized Recycling of Nuclear Fuel (June 2006). |
| Abstract | MIT-NFC-TR-085 | M. Visosky, M.S. Kazimi and P. Hejzlar, Actinide Minimization Using Pressurized Water Reactors (June 2006). |
| Abstract | MIT-NFC-PR-084 | H. Ham and M.W. Golay, An Integrated Methodology for Quantitative Assessment of Proliferation Resistance of Advanced Nuclear Systems Using Probabilistic Methods (May 2006). |
| Abstract | MIT-NFC-PR-083 | T.H. Newton, M.S. Kazimi, and E. Pilat, et al., Development of a Low Enrichment Uranium Core for the MIT Reactor (March 2006). |
| Abstract | MIT-NFC-PR-082 | M.S. Kazimi, P. Hejzlar, et al., High Performance Fuel Design For Next Generation PWRs: Final Report (January 2006). |
| Abstract | MIT-NFC-PR-081 | D. Carpenter and G. Kohse, Experimental Determination of the Thermal Conductivity of a Lead Bismuth, Eutectic-Filled Annulus, June 2005. |
| Abstract | MIT-NFC-PR-080 | H. Feinroth and Y. Yuan, Feasibility of Partial ZrO2 Coatings on the Outer Surface of Annular UO2 Pellets to Control Gap Conductance, June 2005. |
| Abstract | MIT-NFC-TR-079 | P. Ferroni and N.E. Todreas, Steady State Thermal Hydraulic Analysis of Hydride Fueled BWRs (May 2006). |
| Abstract | MIT-NFC-PR-078 | P.R. Diller and N.E. Todreas, Wire Wrapped Fuel Pin Hexagonal Arrays for PWR Service (January 2006). |
| Abstract | MIT-NFC-TR-077 | C. Shuffler, J. Trant, N.E. Todreas, and A. Romano, Thermal Hydraulic and Economic Analysis of Grid-Supported, Hydride- and Oxide-Fueled PWRs (September 2006). |
| Abstract | MIT-NFC-PR-076 | M.S. Kazimi, P. Hejzlar, et al., High Performance Fuel Design For Next Generation PWRs: 4th Annual Report (October 2005). |
| Abstract | MIT-NFC-TR-075 | D. Feng, M.S. Kazimi, and P. Hejzlar, Innovative Fuel Designs for High Power Density Pressurized Water Reactor (September 2005). |
| Abstract | MIT-NFC-PR-074 | M.S. Kazimi, P. Hejzlar, et al., High Performance Fuel Design For Next Generation PWRs: 15th Quarterly Report (August 2005). |
| Abstract | MIT-NFC-PR-073 | M.S. Kazimi, P. Hejzlar, et al., High Performance Fuel Design For Next Generation PWRs: 14th Quarterly Report (April 2005). |
| Abstract | MIT-NFC-PR-072 | M.S. Kazimi, P. Hejzlar, et al., High Performance Fuel Design For Next Generation PWRs: 13th Quarterly Report (January 2005). |
| Abstract | MIT-NFC-TR-071 | 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). |
| Abstract | MIT-NFC-TR-070-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 (December 2004, revised June 2005). |
| Abstract | MIT-NFC-TR-069 | 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). |
| Abstract | MIT-NFC-PR-068 | M.S. Kazimi & P. Hejzlar, High Performance Fuel Design for Next Generation PWRs: 3rd Annual Report (October 2004). |
| Abstract | MIT-NFC-TR-067 | Y. Yuan, M.S. Kazimi, and P. Hejzlar, The Design of High Power Density Annular Fuel for LWRs (September 2004). |
| Abstract | MIT-NFC-PR-066 | M.S. Kazimi et al., High Performance Fuel Design For Next Generation PWRs: 11th Quarterly Report (July 2004). |
| Abstract | MIT-NFC-TR-065 | M. Todosow and M. Kazimi, Optimization of Heterogeneous Utilization of Thorium in PWRs to Enhance Proliferation Resistance and Reduce Waste (July 2004). |
| Abstract | MIT-NFC-TR-064 | 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). |
| Abstract | MIT-NFC-TR-063 | Xu, Z., Y. Otsuka, P. Hejzlar, M.J. Driscoll, and M.S. Kazimi, Neutronic Design of PWR Cores with High Performance Annular Fuel (May 2004). |
| Abstract | MIT-NFC-PR-062 | M.S. Kazimi et al., High Performance Fuel Design For Next Generation PWRs: 10th Quarterly Report (April 2004). |
| Abstract | MIT-NFC-TR-061 | E. Parent, N.E. Todreas, and M.J. Driscoll, Nuclear Fuel Cycles for Mid-centruy Deployment (December 2003). |
| Abstract | MIT-NFC-PR-061 | M.S. Kazimi et al., High Performance Fuel Design For Next Generation PWRs: 9th Quarterly Report (January 2004). |
| Abstract | MIT-NFC-PR-060 | Eugene Shwageraus, Pavel Hejzlar and Mujid S. Kazimi, Optimization of the LWR Nuclear Fuel Cycle for Minimum Waste Production (October 2003). |
| Abstract | MIT-NFC-PR-059 | Antonino Romano, Pavel Hejzlar and Neil E. Todreas, Optimization of Actinide Transmutation in Innovative Lead-Cooled Fast Reactors (October 2003). |
| Abstract | MIT-NFC-PR-058 | M.S. Kazimi et al., High Performance Fuel Design for Next Generation PWRs, 2nd Annual Report (August 2003). |
| Abstract | MIT-NFC-TR-057 | D. Wang, M.S. Kazimi, and M.J. Driscoll, Optimization of a Heterogeneous Thorium-Uranium Core Design for Pressurized Water Reactors (July 2003). |
| Abstract | MIT-NFC-PR-056 | M.S. Kazimi et al., High Performance Fuel Design for Next Generation PWRs, 7th Quarterly Report (May 2003). |
| Abstract | MIT-NFC-TR-055 | Y. Long, Y. Zhang, and M.S. Kazimi, Inert Matrix Materials as Hosts of Actinide Nuclear Fuels (March 2003). |
| Abstract | MIT-NFC-PR-054 | M.S. Kazimi et al., High Performance Fuel Design for Next Generation PWRs, 6th Quarterly Report (March 2003). |
| Abstract | MIT-NFC-TR-053 | Z. Xu, M.J. Driscoll, and M.S. Kazimi, Design Strategies for Optimizing High Burnup Fuel in Pressurized Water Reactors (July 2003). |
| Abstract | MIT-NFC-TR-052 | 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 (). |
| Abstract | MIT-NFC-PR-051 | M.S. Kazimi et al., High Performance Fuel Design for Next Generation PWRs, 5th Quarterly Report (November 2002). |
| Abstract | MIT-NFC-TR-050 | 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). |
| Abstract | MIT-NFC-TR-049 | E. Schwageraus, Y. Zhang, P. Hejzlar, and M.S. Kazimi, Transmutation of Actinides in PWRs Using Fertile Free Fuels (October 2002). |
| Abstract | MIT-NFC-PR-048 | M.S. Kazimi High Performance Fuel Design for Next Generation PWRs, 1st Annual Report (August 2002). |
| Abstract | MIT-NFC-TR-047 | J.G.B. Saccheri and N.E. Todreas, Core Design Strategy for Long-Life, Epithermal, Water-Cooled Reactors (July 2002). |
| Abstract | MIT-NFC-TR-046 | E. Shwageraus, X. Zhao, P. Hejzlar, M.J. Driscoll, and M.S. Kazimi, Optimization of Micro-Heterogenous Uranium-Thorium Dioxide PWR Fuels for Economics and Enhanced Proliferation Resistance (July 2002). |
| Abstract | MIT-NFC-TR-045 | M. Laughter, P. Hejzlar, and M.S. Kazimi, Self-Protection Characteristics of Uranium-233 in the ThO2 -UO2 PWR Fuel Cycle (July 2002). |
| Abstract | MIT-NFC-TR-044 | 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). |
| Abstract | MIT-NFC-TR-043 | D.K. Thompson, K.F. Hansen and M.S. Kazimi, The Effects of Societal Concerns on the Energy Power Industry (May 2002). |
| Abstract | MIT-NFC-TR-042 | D.S. Sentell, Jr., M.W. Golay, and M.J. Driscoll, A Quantitative Assessment of Nuclear Weapons Proliferation Risk Utilizing Probabilistic Methods (May 2002). |
| Abstract | MIT-NFC-PR-041 | M.S. Kazimi et al., High Performance Fuel Design for Next Generation PWRs, 3rd Quarterly Report (May 2002). |
| Abstract | MIT-NFC-PR-040 | M.S. Kazimi et al., High Performance Fuel Design for Next Generation PWRs, 2nd Quarterly Report (February 2002). |
| Abstract | MIT-NFC-PR-039 | M.S. Kazimi et al., High Performance Fuel Design for Next Generation PWRs, 1st Quarterly Report (November 2001). |
| Abstract | MIT-NFC-TR-038 | H.T. Kim, H.C. No, P. Hejzlar, and M.S. Kazimi, Safety Analysis of the Annular Fuel by RELAP5/MOD3.2( (January 2002). |
| Abstract | MIT-NFC-TR-037 | 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). |
| Abstract | MIT-NFC-TR-036 | Y. Sevestre and K.R. Czerwinski, Characterization of Zirconia Based Thoria-Urania Ceramics for Nuclear Fuel and Waste Applications (January 2002). |
| Abstract | MIT-NFC-TR-035 | V.L. Curran and K.R. Czerwinski, Thorium Oxide Dissolution Kinetics for Hydroxide and Carbonate Complexation (August 2001). |
| Abstract | MIT-NFC-TR-031 | X. Zhao, M.J. Driscoll, and M.S. Kazimi, Micro-Heterogeneous Thorium Based Fuel Concepts for Pressurized Water Reactors (August 2001). |
| Abstract | MIT-NFC-TR-030 | 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). |
| Abstract | MIT-NFC-TR-029 | S.M. Oggianu, M.S Kazimi, and H.C. No, High Burnup Fuels for Advanced Nuclear Reactors (May 2001). |
| Abstract | MIT-NFC-TR-028 | Z. Xu, M.J. Driscoll, and M.S. Kazimi, Systematic Study of Moderation Effects on UO2 Fueled Lattices (May 2001). |
| Abstract | MIT-NFC-TR-027 | X. Zhao, P. Hejzlar, and M.J. Driscoll, Comparison of Code Results for PWR Thorium/Uranium Pin Cell Burnup (November 2000). |
| Abstract | MIT-NFC-TR-026 | 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). |
| Abstract | MIT-NFC-TR-025 | M. Busse and M.S. Kazimi, Thermal and Economic Analysis of Thorium-Based Seed-Blanket Fuel Cycles for Nuclear Power Plants (August 2000). |
| Abstract | MIT-NFC-TR-024 | M.S. Kazimi et al., Advanced Fuel for High Burnup and Proliferation Resistance in Light Water Reactors: Annual Report, Rev. 1 (July 2000). |
| Abstract | MIT-NFC-TR-023 | P.E. Owen and K.R. Czerwinski, Waste Characteristics of Spent Nuclear Fuel From a Pebble Bed Reactor (June 2000). |
| Abstract | MIT-NFC-TR-022 | Y. Yuan, P. Monnier, C.S. Rim, and M.S. Kazimi, Fission Gas Release for Thoria-Urania Fuels: A Preliminary Investigation (September 2000). |
| Abstract | MIT-NFC-TR-021 | S.M. Oggianu and M.S. Kazimi, A Review of Properties of Advanced Nuclear Fuels (February 2000). |
| Abstract | MIT-NFC-TR-020 | 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). |
| Abstract | MIT-NFC-TR-019 | D. Kim, M.S. Kazimi, N.E. Todreas, and M.J. Driscoll, Economic Analysis of the Fuel Cycle of Actinide Burning Systems (February 2000). |
| Abstract | MIT-NFC-TR-018 | M.S. Kazimi, M.J. Driscoll, R.G. Ballinger et al.,Proliferation Resistant, Low Cost, Thoria-Urania Fuel for Light Water Reactors (July 1999). |
| Abstract | MIT-NFC-TR-017 | T. Tatsuro, S.R. Connors, and M.S. Kazimi, The Role of Nuclear Energy in Southeast Asia (June 1999). |
| Abstract | MIT-NFC-TR-016 | 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). |
| Abstract | MIT-NFC-TR-015 | 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). |
| Abstract | MIT-NFC-TR-014 | 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). |
| Abstract | MIT-NFC-TR-013 | 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). |
| Abstract | MIT-NFC-TR-012 | 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). |
| Abstract | MIT-NFC-TR-011 | L. Garcia-Delgado and N.E. Todreas, Improvement in Nuclear Plant Capacity Factors Through Longer Cycle Length Operation: Final Report (July 1998). |
| Abstract | MIT-NFC-TR-010 | D.L. Brodeur, V.T. Angus, and N.E. Todreas, Optimization of Nuclear Power Utility Performance (July 1998). |
| Abstract | MIT-NFC-TR-009 | H.J. MacLean, M.V. McMahon, and M.J. Driscoll, Uranium and Separative Work Utilization in Light Water Reactors (January 1998). |
| Abstract | MIT-NFC-TR-008 | 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). |
| Abstract | MIT-NFC-TR-007 | C.S. Handwerk, M.J. Driscoll, N.E. Todreas, and M.V. McMahon, Economic Analysis of Extended Operating Cycles in Existing LWRs (January 1998). |
| Abstract | MIT-NFC-TR-006 | K.W. Budlong Sylvester, S.A. Simonson, K.W. Wenzel, and M.J. Driscoll, Weapons-Grade Plutonium Disposition: An Alternate Immobilization Strategy (June 1997). |
| MIT-NFC-TR-005 | K.W. Wenzel, Photonuclear Reaction for Simulated Radiation Damage in Nuclear Waste Forms (September 1997). | |
| MIT-NFC-TR-004 | 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). | |
| MIT-NFC-TR-002 | F. Morosan and M.S. Kazimi, Multiattribute Analysis of Alternatives for Hanford Tanks Remediation System (January 1997). | |
| MIT-NFC-TR-001 | 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). |