1 / 66

Martian Surface Reactor Group December 3, 2004

Martian Surface Reactor Group December 3, 2004. Motivation for Mars. “We need to see and examine and touch for ourselves” “…and create a new generation of innovators and pioneers.”. Motivation for MSR. Nuclear Physics/Engineering 101. Nuclear Physics/Engineering 101. Goals.

dallon
Download Presentation

Martian Surface Reactor Group December 3, 2004

An Image/Link below is provided (as is) to download presentation Download Policy: Content on the Website is provided to you AS IS for your information and personal use and may not be sold / licensed / shared on other websites without getting consent from its author. Content is provided to you AS IS for your information and personal use only. Download presentation by click this link. While downloading, if for some reason you are not able to download a presentation, the publisher may have deleted the file from their server. During download, if you can't get a presentation, the file might be deleted by the publisher.

E N D

Presentation Transcript


  1. Martian Surface Reactor GroupDecember 3, 2004

  2. Motivation for Mars • “We need to see and examine and touch for ourselves” • “…and create a new generation of innovators and pioneers.”

  3. Motivation for MSR

  4. Nuclear Physics/Engineering 101

  5. Nuclear Physics/Engineering 101

  6. Goals • Litmus Test • Works on Moon and Mars • 100 kWe • 5 EFPY • Obeys Environmental Regulations • Safe • Extent-To-Which Test • Small Mass and Size • Controllable • Launchable/Accident Safe • High Reliability and Limited Maintenance • Scalability

  7. MSR Components • Core • Nuclear Components, Heat • Power Conversion Unit • Electricity, Heat Exchange • Radiator • Waste Heat Rejection • Shielding • Radiation Protection

  8. 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 Friendly

  9. Habitat Reactor Proposed Mission Architecture

  10. CORE

  11. Core - Design Concept • Design criteria: • 100 kWe reactor on one rocket • 5 EFPY • Low mass • Safely Launchable • Maintenance Free and Reliable

  12. Core - Design Choices • Fast Spectrum, High Temp • Ceramic Fuel – Uranium Nitride, 33.1 w/o enriched • Lithium Heatpipe Coolant • Tantalum Burnable Poison • Hafnium Core Vessel • External Control By Drums • Zr3Si2 Reflector material • TaB2 Control material • Fuel Pin Elements in tricusp configuration

  13. Fuel Pin Heatpipe Tricusp Material Core - Pin Geometry • Fuel pins are the same size as the heat pipes and arranged in tricusp design.

  14. Core – Design Advantages • UN fuel, Ta poison, Re Clad/Structure high melting point, heat transfer, neutronics performance, and limited corrosion • Heat pipes no pumps, excellent heat transfer, reduce system mass. • Li working fluid operates at high temperatures necessary for power conversion unit (1800 K)

  15. 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 – Reactivity Control • Reflector controls neutron leakage • Control drums add little mass to the system and offer high reliability due to few moving parts

  16. Core - Smear Composition

  17. Core - Power Peaking

  18. Operation over Lifetime BOL keff: 0.975 – 1.027 = 0.052 EOL keff: 0.989 – 1.044 = 0.055

  19. Launch Accident Analysis • Worst Case Scenarios: • Oceanic splashdown assuming • Non-deformed core • All heat pipes breached and flooded • Dispersion of all 235U inventory in atmosphere

  20. Launch Accident Results • Total dispersion of 235U inventory (104 kg) will increase natural background radiation by 0.024% • Inadvertent criticality will not occur in any conceivable splashdown scenario

  21. Core Summary • UN fuel, Re clad/structure , Ta poison, Hf vessel, Zr3Si2 reflector • Low burn, 5+ EFPY at 1 MWth, ~100 kWe, • Autonomous control by rotating drums over entire lifetime • Flat temperature profile at 1800K • Subcritical for worst-case accident scenario

  22. Future Work • Investigate further the feasibility of plate fuel element design • Optimize tricusp core configuration • Examine long-term effects of high radiation environment on chosen materials

  23. PCU

  24. PCU – Mission Statement Goals: • Remove thermal energy from the core • Produce at least 100kWe • Deliver remaining thermal energy to the radiator • Convert electricity to a transmittable form Components: • Heat Removal from Core • Power Conversion/Transmission System • Heat Exchanger/Interface with Radiator

  25. PCU – Design Choices • Heat Transfer from Core • Heat Pipes • Power Conversion System • Cesium Thermionics • Power Transmission • DC-to-AC conversion • 22 AWG Cu wire transmission bus • Heat Exchanger to Radiator • Annular Heat Pipes

  26. PCU – Heat Extraction from Core • Heat Pipes from Core: • 127 heat pipes • 1 meter long • 1 cm diameter • Rh wall & wick • 400 mesh wick • 0.5mm annulus for liquid • Li working fluid is Pressurized to boil @ 1800K

  27. PCU – Heat Pipes (2) • Possible Limits to Flow • Entrainment • Sonic Limit • Boiling • Freezing • Capillary • Capillary force limits flow:

  28. PCU - Thermionics • Thermionic Power Conversion Unit • Mass: 240 kg • Efficiency: 10%+ • 1.2MWt -> 125kWe • Power density: 10W/cm2 • Surface area per heat pipe: 100 cm2

  29. PCU – Thermionics Design

  30. PCU - Thermionics Issues & Solutions • Creep @ high temp • Set spacing at 5 mm • Used ceramic spacers • Cs -> Ba conversion due to fast neutron flux • 0.01% conversion expected over lifetime • Collector back current • TE = 1800K, TC = 950K

  31. PCU – Power Transmission • D-to-A converter: • 25 x 5kVA units • 360kg total • Small • Transmission Lines: • AC transmission • 25 x 22 AWG Cu wire bus • 500kg/km total • 83.5:1 Transformers increase voltage to 10,000V • 1,385kg total for conversion/transmission system

  32. PCU – Heat Exchanger to Radiator • Heat Pipe Heat Exchanger

  33. PCU – Failure Analysis • Very robust system • Large design margins in all components • Failure of multiple parts still allows for ~90% power generation & full heat extraction from core • No possibility of single-point failure • Each component has at least 25 separate, redundant pieces • Maximum power loss due to one failure – 4% • Maximum cooling loss due to one failure – 0.79%

  34. PCU – Future Work • Improving Thermionic Efficiency • Material studies in high radiation environment • Scalability to 200kWe and up • Using ISRU as thermal heat sink

  35. Radiator

  36. Objective • Design a radiator to dissipate excess heat from a nuclear power plant located on the surface of the Moon or Mars.

  37. Goals • Small mass and area • Minimal control requirement • Maximum accident safety • High reliability

  38. Decision Methodology • Past Concepts • SP-100 • SAFE-400 • SNAP-2 • SNAP-10A • Helium-fed • Liquid Droplet • Liquid Sheet

  39. Component Design • Heat pipes • Carbon-Carbon shell • Nb-1Zr wick • Potassium fluid • Panel • Carbon-Carbon composite • SiC coating

  40. Structural Design • Dimensions • Height 3 m • Diameter 4.8 m • Area 39 m2 • Mass • Panel 200 kg • Heat pipes 60 kg • Supports 46 kg

  41. Support • Supports • Titanium • 8 radial beams • 3 circular strips

  42. Analysis • Models • Isothermal • Linear Condenser • Comparative Area • Moon 39 m2 • Mars 38.6 m2

  43. Future • Analysis of transients • Model heat pipe operation • Conditions at landing site • Manufacturing

  44. Shielding

  45. Shielding - Design Concept • Dose rate on Moon & Mars is ~14 times higher than on Earth • Goal: • Reduce dose rate to between 0.6 - 5.7 mrem/hr • Neutrons and gamma rays emitted, requiring two different modes of attenuation

  46. Shielding - Constraints • Weight limited by landing module (~2 MT) • Temperature limited by material properties (1800K) Courtesy of Jet Propulsion Laboratory

  47. Shielding - Design Choices Neutron shielding Gamma shielding boron carbide (B4C) shell (yellow) Tungsten (W) shell (gray) 40 cm 12 cm • Total mass is 1.97 MT • Separate reactor from habitat • Dose rate decreases as 1/r2 for r >> 50cm - For r ~ 50 cm, dose rate decreases as 1/r

  48. Shielding - Dose w/o shielding • Near core, dose rates can be very high • Most important component is gamma radiation

  49. Shielding - Neutrons

  50. Shielding - Neutrons (2)

More Related