Nuclear Reactors for The Moon and MarsMSR MotivationNuclear Physics/Engineering 101Slide 4Proposed Mission ArchitectureMSR MissionMSR ComponentsCORECore - Design ConceptCore - Design ChoicesCore - Design SpecificationsCore - Design Specifications (2)Core - Design Specifications (3)Core - Future WorkPCUPCU – Design ConceptPCU – Design ChoicesPCU – Design SpecificationsPCU - Design Specifications (2)PCU - Design Specifications (3)PCU - Decision Specifications (4)PCU – Future WorkRadiatorRadiator – Design ConceptRadiator – Design ChoicesRadiator – Design Choices (2)Radiator – Design SpecificationsRadiator - Future WorkShieldingShielding - Design ConceptShielding - Design ChoicesShielding - ConstraintsShielding - GeometryShielding - Future WorkReactor Mass BreakdownMSR Group Expanding Frontiers with Nuclear Technology Tyler Ellis [email protected] Michael Short [email protected] Engineering DepartmentMassachusetts Institute of Technology Martian Surface Reactor Group Nuclear Reactors for The Moon and MarsTyler EllisMichael ShortMartian Surface Reactor GroupNovember 14, 2004MSR Group, 11/14/2004Slide 2Nuclear Engineering DepartmentMassachusetts Institute of Technology MSR MotivationMSR Group, 11/14/2004Slide 3Nuclear Engineering DepartmentMassachusetts Institute of Technology Nuclear Physics/Engineering 101MSR Group, 11/14/2004Slide 4Nuclear Engineering DepartmentMassachusetts Institute of Technology Nuclear Physics/Engineering 101MSR Group, 11/14/2004Slide 5Nuclear Engineering DepartmentMassachusetts Institute of Technology Proposed Mission ArchitectureHabitat ReactorMSR Group, 11/14/2004Slide 6Nuclear Engineering DepartmentMassachusetts Institute of Technology MSR Mission•Nuclear Power for the Martian Surface–Test on Lunar Surface•Design characteristics of MSR–Safe and Reliable–Light and Compact–Launchable and Accident Resistant –Environmentally FriendlyMSR Group, 11/14/2004Slide 7Nuclear Engineering DepartmentMassachusetts Institute of Technology MSR Components•Core–Nuclear Components, Heat•Power Conversion Unit–Electricity, Heat Exchange•Radiator–Waste Heat Rejection•Shielding–Radiation ProtectionMSR Group, 11/14/2004Slide 8Nuclear Engineering DepartmentMassachusetts Institute of Technology COREMSR Group, 11/14/2004Slide 9Nuclear Engineering DepartmentMassachusetts Institute of Technology Core - Design Concept•Develop a 100 kWe reactor with a 5 full-power-year lifetime•Evaluation of options were based on design criteria:–Low mass–Launchability–Safety–High ReliabilityMSR Group, 11/14/2004Slide 10Nuclear Engineering DepartmentMassachusetts Institute of Technology Core - Design Choices•Fast Spectrum•Ceramic Fuel – Uranium Nitride, 35 w/o enriched•Tantalum Burnable Poison•Liquid Lithium Heatpipe Coolant•Fuel Pin Elements in tricusp configuration•External control using drums•Zr3Si2 Reflector material•TaB2 Control materialMSR Group, 11/14/2004Slide 11Nuclear Engineering DepartmentMassachusetts Institute of Technology Core - Design Specifications•UN fuel and Ta poison were chosen for heat transfer, neutronics performance, and limited corrosion•Heatpipes eliminate the need for pumps, have excellent heat transfer, and reduce system mass. •Li working fluid operates at high temperatures necessary for power conversion unit, 1800KMSR Group, 11/14/2004Slide 12Nuclear Engineering DepartmentMassachusetts Institute of Technology Core - Design Specifications (2)•Fuel pins are the same size as heatpipes and arranged in tricusp designHeatpipeFuel PinTricusp MaterialMSR Group, 11/14/2004Slide 13Nuclear Engineering DepartmentMassachusetts Institute of Technology Core - Design Specifications (3)•Reflector controls neutron leakage•Control drums add little mass to the system and offer high reliability due to few moving partsReflectorCoreFuel PinFuelReflectorZr3Si2 ReflectorTotal Mass: 1892kg37 cm99cm10cmRadial ReflectorControl DrumReflector and Core Top-Down ViewMSR Group, 11/14/2004Slide 14Nuclear Engineering DepartmentMassachusetts Institute of Technology Core - Future Work•Perform U235 enrichment versus system mass analysis•Investigate further the feasibility of plate fuel element design•Develop comprehensive safety analysis for launch accidentsMSR Group, 11/14/2004Slide 15Nuclear Engineering DepartmentMassachusetts Institute of Technology PCUMSR Group, 11/14/2004Slide 16Nuclear Engineering DepartmentMassachusetts Institute of Technology PCU – Design ConceptGoals:–Remove thermal energy from the core–Produce at least 100kWe–Deliver remaining thermal energy to the radiatorComponents:–Heat Removal from Core–Power Conversion System–Power Transmission System–Heat Exchanger/Interface with RadiatorMSR Group, 11/14/2004Slide 17Nuclear Engineering DepartmentMassachusetts Institute of Technology PCU – Design Choices•Heat Transfer from Core–Heat Pipes•Power Conversion System–Cesium Thermionics•Power Transmission–DC-to-AC conversion–OOOO gauge Cu wire transmission•Heat Exchanger to Radiator–Annular Heat PipesMSR Group, 11/14/2004Slide 18Nuclear Engineering DepartmentMassachusetts Institute of Technology PCU – Design Specifications•Heat Pipes from Core:–1 meter long–1 cm diameter–100 heat pipes–Molybdenum Pipes–Lithium Fluid•Boiling point @ STP: 1615K•Pressurized to boil @ 1800KCOREMSR Group, 11/14/2004Slide 19Nuclear Engineering DepartmentMassachusetts Institute of Technology PCU - Design Specifications (2)•Thermionic Power Conversion Unit–Mass: 250 kg–Efficiency: 10%+•1MWt -> 100kWe–Power density: 10W/cm2 –Surface area per heat pipe: 100 cm2MSR Group, 11/14/2004Slide 20Nuclear Engineering DepartmentMassachusetts Institute of Technology PCU - Design Specifications (3)•Power Transmission–D-to-A converter:•20 x 5000VA units •300kg total•Small–Transmission Lines:•AC transmission•OOOO gauge Cu wire•1kg/mReactorMSR Group, 11/14/2004Slide 21Nuclear Engineering DepartmentMassachusetts Institute of Technology PCU - Decision Specifications (4)•Heat Pipe Heat ExchangerMSR Group, 11/14/2004Slide 22Nuclear Engineering DepartmentMassachusetts Institute of Technology PCU – Future Work•Improving Thermionic Efficiency•Material behavior in high radiation environment•Heat pipe failure analysis•Scalability to 200kWe•Using ISRU as thermal heat sinkMSR Group, 11/14/2004Slide 23Nuclear Engineering DepartmentMassachusetts Institute of