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. 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. 2014.
Safety of Light Water Reactor Fuel with Silicon Carbide Cladding. Advanced Nuclear Power Program. MIT-ANP-TR-150. 2014.
Silicon Carbide Performance as Cladding for Advanced Uranium and Thorium Fuels for Light Water Reactors. Advanced Nuclear Power Program. MIT-ANP-TR-149. 2014.
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. 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. 2013.
Reactor Physics Assessment of Thick Silicon Carbide Clad PWR Fuels. Advanced Nuclear Power Program. MIT-ANP-TR-148. 2013.
Water Use in the Nuclear Fuel Cycle. Nuclear Energy and Sustainability Program. MIT-NES-TR-017. 2013.
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. 2012.
Development Of Fission Gas Swelling And Release Models For Metallic Nuclear Fuels. Nuclear Fuel Cycle Program. MIT-NFC-TR-130, Revision 1. 2012.
Development of Optimized Core Design and Analysis Methods for High Power Density BWRs. Advanced Nuclear Power Program. MIT-ANP-TR-145. 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. 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. 2012.
Fluoride-Salt-Cooled High-Temperature Reactors (FHRs) For Power and Process Heat. Advanced Nuclear Power Program. MIT-ANP-TR-143. 2012.
An Improved Structural Mechanics Model For The Frapcon Nuclear Fuel Performance Code. Nuclear Fuel Cycle Program. MIT-NFC-TR-129. 2012.
Innovative Design of Uranium Startup Fast Reactors. Advanced Nuclear Power Program. MIT-ANP-TR-146. 2012.
Integrated Fuel Performance And Thermal-Hydraulic Sub-Channel Models For Analysis Of Sodium Fast Reactors. Nuclear Fuel Cycle Program. MIT-NFC-TR-132. 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. 2012.
MCODE-3: Time-Dependent Depletion Isotopics with MCNP-5 and SCALE-6.1. Nuclear Fuel Cycle Program. MIT-NFC-TR-131. 2012.
Nuclear Geothermal Heat Storage: Choosing the Geothermal Heat Transfer Fluid. Nuclear Energy and Sustainability Program. MIT-NES-TR-016. 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. 2012.
Sensitivity Analysis and Optimization of the Nuclear Fuel Cycle: A Systematic Approach. Nuclear Fuel Cycle Program. MIT-NFC-TR-133. 2012.
Separate Effects of Surface Roughness, Wettability and Porosity on Boiling Heat Transfer and Critical Heat Flux and Optimization of Boiling Surfaces. Advances in Nuclear Energy Fundamentals. MIT-ANED-TR-003. 2012.
Alternatives for Sodium Fast Reactor Cost-Effective Design Improvements. Advanced Nuclear Power Program. MIT-ANP-TR-141. 2011.