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Forsberg C., Curtis D., Stempien J., MacDonald R., Peterson P..  2014.  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. Advanced Nuclear Power Program. MIT-ANP-TR-153
Forsberg C., Hu L-W., Richard J., Romatoski R., Forget B., Stempien J., Ballinger R..  2014.  Fluoride-Salt-Cooled High-Temperature Test Reactor (FHTR): Goals, Options, Ownership, Requirements, Design, Licensing, and Support Facilities . Advanced Nuclear Power Report Series. MIT-ANP-TR-154
Nguyen N.T, Todreas N.E.  2014.  An Inverted Pressurized Water Reactor Design With Twisted-Tape Swirl . Advanced Nuclear Power Report Series . MTI-ANP-TR-156
Guyer BL, Golay MJ.  2014.  Nuclear Power Plant Performance Assessment Pertaining to Plant Aging in France and the United States. Nuclear Systems Enhanced Performance (NSP) Series. MIT-NSP-TR-032
Minck MJ, Forsberg C.  2014.  Preventing Fuel Failure for a Beyond Design Basis Accident in a Fluoride Salt Cooled High Temperature Reactor. Advanced Nuclear Power Program. MIT-ANP-TR-151
Lee YH, McKrell T, Kazimi MS.  2014.  Safety of Light Water Reactor Fuel with Silicon Carbide Cladding. Advanced Nuclear Power Program. MIT-ANP-TR-150
Sukjai Y, Pilat E, Shirvan K, Kazimi MS.  2014.  Silicon Carbide Performance as Cladding for Advanced Uranium and Thorium Fuels for Light Water Reactors. Advanced Nuclear Power Program. MIT-ANP-TR-149
Briccetti A., Buongiorno J., Golay M., Todreas N..  2014.  Siting of an Offshore Floating Nuclear Power Plant. Advanced Nuclear Power Report Series. MIT-ANP-TR-152
Nguyen N.T., Chen S-K, Todreas NE.  2013.  Evaluation of Existing Correlations for the Prediction Of Pressure Drop in Wire-Wrapped Hexagonal Array Pin Bundles. Advances in Nuclear Engineering Disciplines. MIT-ANED-TR-004
Forsberg C, Hu L-wen, Peterson PF, Sridharan K.  2013.  Fluoride-Salt-Cooled High-Temperature Reactors (FHRs) for Base-Load and Peak Electricity, Grid Stabilization, and Process Heat. Advanced Nuclear Power Program. MIT-ANP-TR-147
Bloore DA, Pilat E, Kazimi MS.  2013.  Reactor Physics Assessment of Thick Silicon Carbide Clad PWR Fuels. Advanced Nuclear Power Program. MIT-ANP-TR-148
Stempien JD, Meteyer H, Kazimi MS.  2013.  Water Use in the Nuclear Fuel Cycle. Nuclear Energy and Sustainability Program. MIT-NES-TR-017
Arment TW, Todreas NE, Bergles AE.  2012.  Critical Heat Flux and Pressure Drop Correlations for Tubes Containing Multiple Short-Length Twisted-Tape Swirl Promoters. Advances in Nuclear Engineering Disciplines. MIT-ANED-TR-002
Andrews N, Karahan A, Kazimi MS.  2012.  Development Of Fission Gas Swelling And Release Models For Metallic Nuclear Fuels. Nuclear Fuel Cycle Program. MIT-NFC-TR-130, Revision 1
Shirvan K, Kazimi MS.  2012.  Development of Optimized Core Design and Analysis Methods for High Power Density BWRs. Advanced Nuclear Power Program. MIT-ANP-TR-145
Sugrue R, McKrell T, Buongiorno J.  2012.  The Effects of Orientation Angle, Subcooling, Heat Flux, Mass Flux, and Pressure on Bubble Growth and Detachment in Subcooled Flow Boiling. Advances In Nuclear Engineering Disciplines. MIT-ANED-TR-001
Horelik NE, Forget B, Newton T.  2012.  Expanding and Optimizing Fuel Management and Data Analysis Capabilities of MCODE-FM in Support of MIT Research Reactor (MITR-II) LEU Conversion. MIT Research Reactor Upgrade. MIT-MITRR-TR-010
Forsberg CW, Hu L-wen, Peterson PF, Allen T.  2012.  Fluoride-Salt-Cooled High-Temperature Reactors (FHRs) For Power and Process Heat. Advanced Nuclear Power Program. MIT-ANP-TR-143
Mieloszyk A J, Kazimi MS.  2012.  An Improved Structural Mechanics Model For The Frapcon Nuclear Fuel Performance Code. Nuclear Fuel Cycle Program. MIT-NFC-TR-129
Fei T, Shwageraus E, Driscoll MJ.  2012.  Innovative Design of Uranium Startup Fast Reactors. Advanced Nuclear Power Program. MIT-ANP-TR-146
Fricano JW, Buongiorno J.  2012.  Integrated Fuel Performance And Thermal-Hydraulic Sub-Channel Models For Analysis Of Sodium Fast Reactors. Nuclear Fuel Cycle Program. MIT-NFC-TR-132
DeWitt GL, McKrell T, Buongiorno J, Hu L-wen.  2012.  Investigation of Downward, Facing Critical Heat Flux, with Water-Based, Nanofluids for In-Vessel, Retention Applications. Advanced Nuclear Power Program. MIT-ANP-TR-144
Gerrity TP, Forget B, Newton T.  2012.  MCODE-3: Time-Dependent Depletion Isotopics with MCNP-5 and SCALE-6.1. Nuclear Fuel Cycle Program. MIT-NFC-TR-131
Kulhanek M, Forsberg CW, Driscoll MJ.  2012.  Nuclear Geothermal Heat Storage: Choosing the Geothermal Heat Transfer Fluid. Nuclear Energy and Sustainability Program. MIT-NES-TR-016
Kwak T, Golay MW.  2012.  Nuclear Non-Proliferation Regime Effectiveness: An Integrated Methodology for Analyzing Highly Enriched Uranium Production Scenarios at Gas Centrifuge Enrichment Plants. Nuclear Fuel Cycle Program. MIT-NFC-TR-128