A Transient Simulation Test Rig for Heat Pipe Cooled Space Nuclear Reactors Adam Wheeler, Andrew...
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![Page 1: A Transient Simulation Test Rig for Heat Pipe Cooled Space Nuclear Reactors Adam Wheeler, Andrew Klein Department of Nuclear Engineering & Radiation Health.](https://reader036.fdocuments.net/reader036/viewer/2022081511/56649c6a5503460f949183bc/html5/thumbnails/1.jpg)
A Transient Simulation Test Rig for Heat Pipe Cooled Space
Nuclear ReactorsAdam Wheeler, Andrew Klein
Department of Nuclear Engineering & Radiation Health Physics
Oregon State University
February 25, 2013
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Outline
• Introduction• Reference design• Variations from the Reference
Design• Modeling programs
– SolidWorks– STELLA
• Models– Goals– Assumptions
• Results from analysis• Discussion of results• Conclusion and future work• References
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Introduction
• Objective: Develop and analyze a test facility based on a 1 to 10kWe heat-pipe cooled space nuclear reactor
• Goals: – Design a feasible test facility– Predict steady state performance – Predict transient responses
• Method: Use a lumped parameter model and a 3D CAD simulation program for analysis
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Reference Design
• Reference system is a 1 to 10kWe reactor module
• Developed by a collaboration between NASA Glenn and Marshall Research Centers and Los Alamos National Laboratory
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Variations from the Reference Design
Original Design• 1000K sodium heat pipes
in core• 8 to 16 heat pipes from
core to power convertors
• Pin or plate fuel interface to heat pipes
• Direct energy conversion via Stirling engines or Thermoelectrics
• Cone-shaped radiator array
Test Facility• 600K water heat pipes in
core simulator• 8 heat pipes between core
& power convertor simulators
• Stainless steel cylinder interface to heat pipes
• Power conversion thermal absorption simulator
• Cylindrical radiator array
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Modeling Programs
SolidWorks• Used for 3D rendering and
various types of simulations
• Flow Simulation package allows for heat and fluid flow in a time dependent simulation
• Lacks computational stability and speed but can give very detailed results
STELLA• Object oriented flow based
system• Great for modeling the
transfer of some item (heat, chemicals, water, population, etc.) to another location through time
• Lacks accuracy and detail but is very versatile and fast
(STELLA can be made more accurate but quickly reaches a diminishing return in effort and time which makes more complex CFD programs more attractive)
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Limits to the System
• Upper bounds:– 700K in the heat pipes from the core to the ECS– 550K in the radiator array heat pipes– 1600K in the stainless steel cylinders
• Lower bounds:– 600K in the heat pipes from the core to the ECS– 450K in the radiator array heat pipes
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SolidWorks Model Boundary Conditions
• To simulate the affects of convection, a direct heat sink boundary condition was applied which simplified the model
• A heat source was placed in the core simulator’s heater rods
• To model the heat pipes, a custom material with very high conductance at the heat pipe’s operating temperatures was used along with the heat pipe operator in Flow Simulation
• Radiation transfer boundary conditions were placed on the outer surfaces of the model ECS
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Stella ModelAssumptions
• Axial heat transfer is negligible in comparison to radial heat transfer
• Heat transfer to and from sinks and sources can be done with 1D radial methods
• Adiabatic boundary conditions assumed for outer edges of the system
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Stella Model
Core Simulator Cross-section
Energy Conversion Simulator Cross-section
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STELLA Model
• STELLA model uses three basic components– Convertor• Used to control flow and system variables
– Reservoir• Points for collecting the heat passing through system
– Bidirectional flow• Forces directional flow between Reservoirs and • Controlled by connections between Convertors and
Reservoirs
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STELLA Model
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STELLA Model
• The whole thing:
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STELLA Results: Startup
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SolidWorks Results: Startup
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SolidWorks Results: Startup
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STELLA Results: One HP Lost
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STELLA Results: One HP Lost
Increasing Time
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SolidWorks Results: One HP Lost
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SolidWorks Results: One HP Lost
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STELLA Results: Two Consecutive HPs Lost
0 20 40 60 80 100
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625630635640645650655660665
Counterclockwse From Area of Interest in Core
H Wedge 4H Wedge 5H Wedge 6H Wedge 7
Time [s]
Tem
pera
ture
[K]
0 100 200 300 400 500 600 700 800 900 1000 1100 1200 1300 1400625630635640645650655660665
Clockwise From Area of Interest in Core
H Wedge 1H Wedge 16H Wedge 2H Wedge 3
Time [s]
Tem
pera
ture
[K]
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STELLA Results: Two Consecutive HPs Lost
H W
edge
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625
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635
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665
Heater Wedge Temperatures Through Time for the Two Heat Pipes Lost Case
Heater Wedge
Tem
pera
ture
[K]
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SolidWorks Results: Two Consecutive HPs Lost
![Page 24: A Transient Simulation Test Rig for Heat Pipe Cooled Space Nuclear Reactors Adam Wheeler, Andrew Klein Department of Nuclear Engineering & Radiation Health.](https://reader036.fdocuments.net/reader036/viewer/2022081511/56649c6a5503460f949183bc/html5/thumbnails/24.jpg)
SolidWorks Results: Two Consecutive HPs Lost
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STELLA Results: Three Consecutive HPs Lost
0 80 160 240 320 400 480 560 640 720 800 880 960 10401120625635645655665675685695705
Clockwise From Area of Interest in Core
H Wedge 1H Wedge 16H Wedge 2H Wedge 3H Wedge 4
Time [s]
Tem
pera
ture
[K]
0 80 160 240 320 400 480 560 640 720 800 880 960 1040 1120625635645655665675685695705
Counterclockwise From Area of Interest in Core
H Wedge 5H Wedge 6H Wedge 7H Wedge 8H Wedge 9
Time [s]
Tem
pera
true
[K]
![Page 26: A Transient Simulation Test Rig for Heat Pipe Cooled Space Nuclear Reactors Adam Wheeler, Andrew Klein Department of Nuclear Engineering & Radiation Health.](https://reader036.fdocuments.net/reader036/viewer/2022081511/56649c6a5503460f949183bc/html5/thumbnails/26.jpg)
STELLA Results: Three Consecutive HPs Lost
H W
edge
1
H W
edge
2
H W
edge
3
H W
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Heater Wedge Temperatures Through Time for the Three Heat Pipes Lost Case
Heater Wedge
Tem
pera
ture
[K]
![Page 27: A Transient Simulation Test Rig for Heat Pipe Cooled Space Nuclear Reactors Adam Wheeler, Andrew Klein Department of Nuclear Engineering & Radiation Health.](https://reader036.fdocuments.net/reader036/viewer/2022081511/56649c6a5503460f949183bc/html5/thumbnails/27.jpg)
SolidWorks Results: Three Consecutive HPs Lost
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SolidWorks Results: Three Consecutive HPs Lost
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STELLA Results: Opposite HPs Lost0 20 40 60 80 100
120
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625627629631633635637639641643
Resolution Time Data
H Wedge 3H Wedge 4H Wedge 5H Wedge 6
Time [s]
Tem
pera
ture
[K]
H W
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edge
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H W
edge
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H W
edge
16
625627629631633635637639641643
Heater Wedge Temperatures Through Time
Heater Wedge
Tem
pera
ture
[K]
![Page 30: A Transient Simulation Test Rig for Heat Pipe Cooled Space Nuclear Reactors Adam Wheeler, Andrew Klein Department of Nuclear Engineering & Radiation Health.](https://reader036.fdocuments.net/reader036/viewer/2022081511/56649c6a5503460f949183bc/html5/thumbnails/30.jpg)
SolidWorks Results: Opposite HPs Lost
![Page 31: A Transient Simulation Test Rig for Heat Pipe Cooled Space Nuclear Reactors Adam Wheeler, Andrew Klein Department of Nuclear Engineering & Radiation Health.](https://reader036.fdocuments.net/reader036/viewer/2022081511/56649c6a5503460f949183bc/html5/thumbnails/31.jpg)
SolidWorks Results: Opposite HPs Lost
![Page 32: A Transient Simulation Test Rig for Heat Pipe Cooled Space Nuclear Reactors Adam Wheeler, Andrew Klein Department of Nuclear Engineering & Radiation Health.](https://reader036.fdocuments.net/reader036/viewer/2022081511/56649c6a5503460f949183bc/html5/thumbnails/32.jpg)
Discussion of Results
• STELLA results:– System is fast in responding to heat transients– Temperature changes as a result of heat pipe
losses are less then 100K• SolidWorks results:– Reasonably agree with the STELLA time and
temperature results, and show in greater detail the temperature differences across the system
![Page 33: A Transient Simulation Test Rig for Heat Pipe Cooled Space Nuclear Reactors Adam Wheeler, Andrew Klein Department of Nuclear Engineering & Radiation Health.](https://reader036.fdocuments.net/reader036/viewer/2022081511/56649c6a5503460f949183bc/html5/thumbnails/33.jpg)
Conclusion and Future Work
• The computational models gave a decent result that can be used for future analysis
• Future work:– Increasing accuracy in STELLA model– Exact design specifications– Cost of actually building the facility– Gravity scaling– Finding a functional variable heat absorption method
![Page 34: A Transient Simulation Test Rig for Heat Pipe Cooled Space Nuclear Reactors Adam Wheeler, Andrew Klein Department of Nuclear Engineering & Radiation Health.](https://reader036.fdocuments.net/reader036/viewer/2022081511/56649c6a5503460f949183bc/html5/thumbnails/34.jpg)
References
Polzin, K. A., & Godfrey, T. J., “Flow Components in a NaK Test Loop Designed to Simulate Conditions on a Nuclear Surface Power Reactor.” AIP Conference Proceedings.Sanzi, J. L., “Thermal Performances of High Temperature Titanium - Water Heat Pipes by Multiple Heat Pipe Manufacturers.” AIP Conference Proceedings. (2007).Sarraf, D. B., & Anderson, W. G., “Heat Pipes for High Temperature Thermal Managment.” IPACK2007. (2007).
Poston, D., Kapernick, R., Dixon, D., Reid, R., Mason, L., “Reactor Module Design for a Kilowatt-Class Space Reactor Power System.” NETS 2012 Conference Proceedings. (2012).El-Genk, M. S., Tounier, J., “High Temperature Water Heat Pipes Radiator for a Brayton Space Reactor Power System.” AIP Conference Proceedings. (2006)Bergman, T. L., Lavine, A. S., Incropera, F. P., Dewitt, D. P., “Fundamentals of Heat and Mass Transfer” 7 th ed.Anderson, W. G., & Tarau, C., “Variable Conductance Heat Pipes for Radioisotope Stirling Systems.” AIP Conference Proceedings.Reay, D., Kew, P., “Heat Pipes.” 5th ed. p107-141.Tarau, C., Anderson, W. G., Miller, W. O., & Ramirez, R., “Sodium VCHP with Carbon-Carbon Radiator for Radioisotope Stirling Systems.” AIP Conference Proceedings.isee Systems, STELLA Systems Thinking for Education and Research. http://www.iseesystems.com/softwares/Education /StellaSoftware.aspxPerez, D. M. , M. A. Lillo, G. S. Chang, G. A. Roth, N. E. Woolstenhulme, D. M. Wachs, “RERTR-10 Irradiation Summary Report.” May 2011.WATLOW, HT FIREROD cylindrical heaters, http://www.watlow.com/index.cfmHoa, C., Demolder, B., Alexandre, A., “Roadmap for developing heat pipes for ALCATEL SPACE’s satellites.” Applied Thermal Engineering. 23 (2003) 1099- 1108.Mascari, F., Vella, G., Woods, BG., D’Auria, F., “Analyses of the OSU-MASLWR Experimental Test Facility.” Science and Technology of Nuclear Installations. (2151-0032) 2012, p.19.Reyes, J. N. Jr., Hochreiter, L., “Scaling analysis for the OSU AP600 test facility (APEX).” Nuclear Engineering and Design. Volume 186, Issues 1-2, 11/1/1998, p. 53-109.Kauffman, AC., Miller, DW., Radcliff, TD., Maupin, KW., Mills, DJ., Penrod, VM., “High-Temperature Test Facility for Reactor In-Core Sensor Testing.” Nuclear Technology. (0029-5450), 11/2002, Volume 140, Issue 2, pp. 222-232.ASRG, “Space Radioisotope Power Systems.” Advanced Stirling Radioisotope Generator. January 2011. http://www.ne.doe.gov/pdfFiles/factSheets/SpaceRadioisotopePowerSystemsASRG.pdf
Questions?