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CORECore - Design ConceptCore - Design ChoicesCore - Design SpecificationsCore - Design Specifications (2)Core - Design Specifications (3)IntegrationLaunch Accident AnalysisLaunch Accident ResultsFuture WorkMSR Group, 11/14/2004Slide 1Nuclear Engineering DepartmentMassachusetts Institute of Technology COREMSR Group, 11/14/2004Slide 2Nuclear 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 3Nuclear Engineering DepartmentMassachusetts Institute of Technology Core - Design Choices•Fast Spectrum•Ceramic Fuel – Uranium Nitride, 33.1 w/o enriched•Tantalum Burnable Poison•Lithium Heatpipe Coolant•Fuel Pin Elements in tricusp configuration•External Control By Drums•Zr3Si2 Reflector material•TaB2 Control materialMSR Group, 11/14/2004Slide 4Nuclear Engineering DepartmentMassachusetts Institute of Technology Core - Design Specifications•UN fuel and Ta poison were chosen for heat transfer, neutronics performance, and limited corrosion•Heat pipes 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: 1800 KMSR Group, 11/14/2004Slide 5Nuclear Engineering DepartmentMassachusetts Institute of Technology HeatpipeFuel PinTricusp MaterialCore - Design Specifications (2)•Fuel pins are the same size as the heat pipes and arranged in tricusp design.MSR Group, 11/14/2004Slide 6Nuclear 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 partsRadial ReflectorControl DrumReflector and Core Top-Down ViewReflectorCoreFuel PinFuelReflectorZr3Si2 ReflectorTotal Mass: 2654kg42 cm88 cm10 cm10 cmReflectorMSR Group, 11/14/2004Slide 7Nuclear Engineering DepartmentMassachusetts Institute of Technology Integration•Insert picture of reactor design from JoeMSR Group, 11/14/2004Slide 8Nuclear Engineering DepartmentMassachusetts Institute of Technology Launch Accident Analysis•Many accidents were considered however, only accidents upon launch could not be prevented by extra safeguards.•Worst Case Scenarios:–Uniform dispersion of all U235 in atmosphere–Undeformed core with all heat pipes ruptured lands in water or wet sandMSR Group, 11/14/2004Slide 9Nuclear Engineering DepartmentMassachusetts Institute of Technology Launch Accident ResultsReflectors Stowed Reflectors DetachedWaterKeff=0.97081±0.00092 Keff=0.95343±0.00109Wet SandKeff=0.97387±0.00095 Keff=0.96458±0.00099•Total Dispersion of the 157 kg of U235 will increase the natural background radiation by 0.0025%•Water and Wet Sand Landing will not result in criticalityMSR Group, 11/14/2004Slide 10Nuclear Engineering DepartmentMassachusetts Institute of Technology Future Work•Investigate further the feasibility of plate fuel element design•Optimize core configuration•Examine long-term effects of high radiation environment on chosen materials•Develop comprehensive safety analysis for launch


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MIT 22 33 - Core

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