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Martian Surface Reactor Group December 3, 2004OVERVIEWMotivation for MSRNeed for Nuclear PowerFission 101MSR MissionDecision GoalsMSR System OverviewCORECore – Goals and ComponentsCore - Design Choices OverviewCore - Pin GeometryCore – Design AdvantagesCore – Dimensions and ControlCore - CompositionCore - Power PeakingOperation over LifetimeLaunch Accident AnalysisLaunch Accident ResultsCore SummaryPCUPCU – Mission StatementPCU – Design ChoicesPCU – Heat Extraction from CorePCU – Heat Pipes (2)PCU - ThermionicsPCU - Thermionics Issues & SolutionsSlide 28PCU – Power TransmissionPCU – Heat Exchanger to RadiatorPCU – Failure AnalysisRadiatorObjectiveEnvironmentRadiator – Design ChoicesComponent DesignComponent Design (2)Structural DesignSlide 39Radiation Interactions with MatterShielding - Design ConceptShielding - ConstraintsShielding - Design ChoicesShielding - Dose w/o shieldingShielding - NeutronsShielding - Neutrons (3)Shielding - GammasShielding - DesignShielding - Design (2)Shielding - Design (3)MSR Assembly SketchMSR MassMass Reduction and Power GainMSR Mission PlanMSR Group Expanding Frontiers with Nuclear TechnologyAdditional SlidesFuture Work – CorePCU – Decision MethodologyPCU – Future WorkRadiator Future WorkAnalysisShielding - Future WorkShielding - Alternative DesignsShielding -Alternative Designs (2)MRS Design AdvantagesMSR CostNuclear Engineering DepartmentMassachusetts Institute of Technology Martian Surface Reactor Group Martian Surface Reactor GroupDecember 3, 2004MSR Group, 12/3/2004Slide 2Nuclear Engineering DepartmentMassachusetts Institute of Technology OVERVIEW•Need for Nuclear Power•Fission 101•Project Description•Description and Analysis of the MSR Systems–Core–Power Conversion Unit (PCU)–Radiator–Shielding•ConclusionMSR Group, 12/3/2004Slide 3Nuclear Engineering DepartmentMassachusetts Institute of Technology Motivation for MSR 10/15/2004 Slide 1Competition Sensitive – Do not distribute outside of NASA / Draper / MIT teamBill [email protected] Concept Exploration and Refinement StudySurface PowerLunar Surface Power OptionsFission ReactorFission Reactor + SolarRadioisotope + SolarSolarChemicalDuration of useElectric Power Level (kWe)Martian Surface Power Options- Solar power becomes much less feasible- Mars further from Sun(45% less power)- Day/night cycle- Dust storms- Too-short Lifetime forMartian missions- Nuclear Power dominates curve for Martian missions.MSR Group, 12/3/2004Slide 4Nuclear Engineering DepartmentMassachusetts Institute of Technology Need for Nuclear PowerMSR Group, 12/3/2004Slide 5Nuclear Engineering DepartmentMassachusetts Institute of Technology Fission 101MSR Group, 12/3/2004Slide 6Nuclear Engineering DepartmentMassachusetts Institute of Technology MSR Mission•Nuclear Power for the Martian Surface–Test on Lunar Surface •Design Criteria–100kWe–5 EFPY–Works on the Moon and MarsMSR Group, 12/3/2004Slide 7Nuclear Engineering DepartmentMassachusetts Institute of Technology Decision Goals•Litmus Test–Works on Moon and Mars–100 kWe –5 EFPY –Obeys Environmental Regulations•Extent-To-Which Test–Small Mass and Size–Controllable –Launchable/Accident Safe–High Reliability and Limited Maintenance–ScalabilityMSR Group, 12/3/2004Slide 8Nuclear Engineering DepartmentMassachusetts Institute of Technology MSR System Overview•Core (54%)–Nuclear Components, Heat•Power Conversion Unit (17%)–Electricity, Heat Exchange•Radiator (4%)–Waste Heat Rejection•Shielding (25%)–Radiation Protection•Total Mass ~8MTMSR Group, 12/3/2004Slide 9Nuclear Engineering DepartmentMassachusetts Institute of Technology COREMSR Group, 12/3/2004Slide 10Nuclear Engineering DepartmentMassachusetts Institute of Technology Core – Goals and Components•Goals–1.2 MWth–1800K•Components–Spectrum –Reactivity Control Mechanism–Reflector–Coolant System–Encapsulating Vessel–Fuel Type/EnrichmentMSR Group, 12/3/2004Slide 11Nuclear Engineering DepartmentMassachusetts Institute of Technology Core - Design Choices OverviewDesign Choice ReasonFast Spectrum, High Temp High Power DensityUN Fuel, 33 w/o enriched High Temperature/BreedingLithium Coolant Power ConversionRe Cladding/Internal Structure Physical PropertiesZr3Si2 Reflector materialNeutron “Mirror”Rotating DrumsAutonomous ControlHafnium Core Vessel Accident ScenarioTricusp Fuel Configuration Superior Heat TransferMSR Group, 12/3/2004Slide 12Nuclear Engineering DepartmentMassachusetts Institute of Technology HeatpipeFuel PinTricusp MaterialCore - Pin Geometry•Fuel pins are the same size as the heat pipes and arranged in tricusp design.•Temperature variation 1800-1890KMSR Group, 12/3/2004Slide 13Nuclear Engineering DepartmentMassachusetts Institute of Technology Core – Design Advantages•UN fuel, Ta absorber, Re Clad/Structure high melting point, heat transfer, neutronics performance, and limited corrosion•Heat pipes pumps not required, excellent heat transfer, small system mass•Li working fluid operates at high temperatures necessary for power conversion unit (1800K)MSR Group, 12/3/2004Slide 14Nuclear Engineering DepartmentMassachusetts Institute of Technology Core – Dimensions and Control•Reflector controls neutron leakage•Small core, total mass ~4.3 MTReflectorCoreFuel PinFuelReflector42 cm89 cm10 cm10 cmReflectorMSR Group, 12/3/2004Slide 15Nuclear Engineering DepartmentMassachusetts Institute of Technology Core - CompositionMaterial Purpose Volume Fraction7Li Coolant 0.07315N Fuel Compound 0.353NatNb Heatpipe 0.076181Ta Poison 0.038NatRe Cladding/Structure 0.110235U Fissile Fuel 0.117238U Fertile Fuel 0.233MSR Group, 12/3/2004Slide 16Nuclear Engineering DepartmentMassachusetts Institute of Technology Core - Power PeakingPeaking Factor, F(r)00.20.40.60.811.21.4-22 -20 -18 -16 -14 -12 -10 -8 -6 -4 -2 0 2 4 6 8 10 12 14 16 18 20 22Core Radius (cm)F(r)31.1InDrumsRPPR24.1OutDrumsRPPFMSR Group, 12/3/2004Slide 17Nuclear Engineering DepartmentMassachusetts Institute of Technology Operation over LifetimeBOL keff: 0.975 – 1.027EOL keff: 0.989 – 1.044effkD= 0.052effkD= 0.055Reactivity over Lifetime0.940.960.981.001.021.041.061.080 1 2 3 4 5 6Years of OperationKeffMSR Group, 12/3/2004Slide 18Nuclear Engineering DepartmentMassachusetts Institute of Technology Launch Accident Analysis•Worst Case Scenario:–Oceanic splashdown assuming•Non-deformed core •All


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MIT 22 33 - Nuclear Power

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