MSR Group, 11/14/2004 - PowerPoint PPT Presentation

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MSR Group, 11/14/2004

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Nuclear Engineering Department Massachusetts Institute of Technology * * Title: Nuclear Reactors for The Moon and Mars Author: Michael Stawicki Last modified by: – PowerPoint PPT presentation

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Title: MSR Group, 11/14/2004


1
CORE
2
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

3
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

4
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

5
Core - Design Specifications (2)
  • Fuel pins are the same size as the heat pipes and
    arranged in tricusp design.

6
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

7
Integration
  • Insert picture of reactor design from Joe

8
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

9
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

Reflectors Stowed Reflectors Detached
Water Keff0.970810.00092 Keff0.953430.00109
Wet Sand Keff0.973870.00095 Keff0.964580.00099
10
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
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