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CORE - PowerPoint PPT Presentation


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CORE. 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 Reliability. Core - Design Choices. Fast Spectrum Ceramic Fuel – Uranium Nitride, 33.1 w / o enriched

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core design concept
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 Reliability
core design choices
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 material
core design specifications
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 K
core design specifications 2

Fuel Pin

Heatpipe

Tricusp Material

Core - Design Specifications (2)
  • Fuel pins are the same size as the heat pipes and arranged in tricusp design.
core design specifications 3

88 cm

Fuel Pin

Reflector and Core Top-Down View

10 cm

Reflector

Control Drum

Reflector

42 cm

Fuel

Core

10 cm

Reflector

Zr3Si2 Reflector

Total Mass: 2654kg

Radial Reflector

Core - Design Specifications (3)
  • Reflector controls neutron leakage
  • Control drums add little mass to the system and offer high reliability due to few moving parts
integration
Integration
  • Insert picture of reactor design from Joe
launch accident analysis
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 sand
launch accident results
Launch Accident Results
  • 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 criticality
future work
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 accidents