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Extrapolation of GDT Results to a DT Fusion Neutron Source for Fusion
Materials Testing
e
Tom Simonen, U. Calif., Berkeley8th International Conference on Open
Magnetic SystemsJuly 5-9, 2010 Novosibirsk, Russia
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US Fusion Program (2010)
• Establish the Scientific Basis– Burning Plasma (ITER)– Plasma Control (DIIID, EAST,KSTAR, JT60)– Materials Science
• Plasma Material Interactions• Neutron Material Interactions• ………..
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US Mirror Assessment• Stimulated by new Gamma-10 and GDT Results• Formed a Mirror Study Group (Virtual Meetings)
– 10 Institutions, 25 individuals• Held Two Workshops
– Physics and Technology• Held a Magnetic-Mirror Mini-Conference
– At 2009 American Phys. Society DPP Meeting– Participated in Numerous DOE Planning Meetings
• Proposed International Collaborations– Russia, Japan, China
• Tutorial Talk at 2010 APS Meeting– Dmitri Ryutov
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ITER is under Construction China, EU, India, Korea, Japan, Russia, US
(
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FUSION CHALLENGES (Sci.Am., March 2010)“Before fusion can be a viable energy source, scientists must overcome a number of problems.
Heat: Materials that face the reactions must withstand extremely high temperatures for years on end.
Structure: The high-energy neutrons coming from fusion reactions turn ordinary materials brittle.
Fuel: A fusion reactor will have to “breed” its own tritium in a complex series of reactions.
Reliability: Laser reactors produce only intermittent blasts; magnet based systems must maintain aplasma for weeks, not seconds.”
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Fusion Neutrons Damage Materials
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Fusion Materials Must Withstand Neutron Bombardment
• Three Options toQualify Materials:– Accelerator Based (coupons)– Mirror Based (Blanket Sub-modules}– Tokamak Based (Blanket Modules)
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RTNS Accelerator Facility(US Rotating Target Neutron Source)
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RTNS Accelerator
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IFMIF Design by EU & Japan
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Tokamak Component Test Facility (US Design)
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Tokamak Fusion Nuclear Science Facility (US Design)
fnsf
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TDF
1980’s Mirror Based Neutron Source Designs
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Axisymmetric Magnetic Mirror
Gas Dynamic Trap (GDT) ConceptA.A. Ivanov, Fus. Sci. & Tech. 57, (2010), 320
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GDT Schematic
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GDT DD-Neutron Axial Profile(Agrees with Computer Simulation)
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Electron Temperature vs Time(End Expansion = 100)
17
- H-plasma n ≈ 1.5 x 1013 cm-3 with H-NBI
- H-plasma n ≈ 2.5 x 1013 cm-3 with H-NBI
- D-plasma n ≈ 2.5÷3 x 1013 cm-3 with H-NBI
- H-plasma n ≈ 1.2 x 1013 cm-3 with H-NBI min gas puff
- H-plasma n ≈ 3 x 1013 cm-3 with D-NBI
- H-plasma n ≈ 3.5÷3 x 1013 cm-3 with H-NBI
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Neutron Flux Increases with Te(Now GDT Te = 0.25 keV so Flux = 0.4 MW/m2)
(ITER Goal = 0.5 MW/m2, Fluence = 0.3 MW-yrs/m2)
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A Russian Neutron Source DesignA MW of Fusion Power for Weeks
Neutron Flux ~ 2 MW/m2 Test Area ~ 1 m2I
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A DTNS Showing Magnets, Shielding ,Neutral Beams, and Material Samples
(Bobouch, Fusion Science & Tech. 41 (2002) p44)
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With Today’s GDT ElectronTemperature (0.25 keV)
• DTNS Neutron Flux 80% of ITER
• DTNS Neutron Fluence in One Year Exceeds that in ITERs Lifetime
Note: DTNS does Not Address ITER’s Burning Plasma Physics or Full-scale Blanket Module Testing
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Design DTNS from GDT Results
• Same Physical Size– L, r
• Higher Mag. Field, NBI Energy and Power– 1.2 T, 80 keV, 40 MW
• Same Dimensionless Parameters– Beta, B(z), L/ai, r/ai, Te/Ei
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Same-Size & Dimensionless Scaling
GDT DTNS
B, Tesla 0.3 1.0
Eb, keV 20 80
Pb, MW 5 30
Beta (%) 60 60
Mirror Ratio, R 17 17
Length, & Radius, cm 7 00 , 6 700 , 6
Radius / Gyro-radius 2 2
Debye Length, 10-3 cm 2 2
Te/Eb , % 1 1
Collisionality 5 1 Marginal
f(pe)/f(ci) 6 0.6 More Microstable
v(b)/v(Alfven) 1.6 0.5 More Alfven Stab
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A Possible Next Step
A Phased Approach (Physics >> PMI >> D-T Neutrons)
B = 0.6 Tesla – 1 s NBI 40 keV – 1 MW – 1 s
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Key DTNS Scientific Issues
• Increase Electron Temperature– Now Te ~ 0.25 keV (0.4 MW/m2 neutrons)– Demonstrate Te > 0.5 keV (80 keV NBI)
• Confirm MHD Stabilization Physics– Diagnostics and Simulation
• Evaluate DTNS Design– Simultaneous Neutron and PMI Testing?
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Key DTNS Technical Issues
• High Neutral Beam Power • Large Tritium Recycling
• Consider Simple Tandem-Mirror Concept (GDT-SHIP concept)
• Small Axisymmetric End-Cells Reduce Plasma End Losses– Reduces overall neutral beam power – Reduces Tritium Recycling
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A Tandem-Mirror Neutron Source (TNS) (Based on TMX Data and the GDT-SHIP Concept)
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TNS Features
• Plug to Center-cell density ratio 4– To reduce end loss 4-fold
• Plug Mirror ratio 3– To reduce AIC and loss cone size
• Plug NB injected at mirror ratio 1.3– For AIC Stability
• Neutral Beam Power (MW) 20– Half of DTNS
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TNS Parameters
• Maximum Miagnetic Field, 20 Tesla• Plug Mirror Ratio, 3• Central-Cell Magnetic Field, 1.2 Tesla• Central-Cell NBI Power, 10 MW• End-Cell NBI Power, 5 MW each• Electron Temperature, 2 keV
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TNS Challenges(GDT-SHIP can address many issues)
• Electron Temperature• MHD Stability at Higher Te• Energetic Ion iMicro-stability• Tritium Retention• Detailed Modeling Needed
• GDT – SHIP can address many issues
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Summary
• A DT Neutron Source (DTNS) can have the same Physical-Size and the same Dimensionless -Size as GDT
• A Simple Tandem Mirror Neutron Source (TNS) Reduces Tritium Reprocessing 4-fold and Reduces the Neutral Beam Power 2-fold.
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We Can Produce 1 MW of Fusion Power Sustained for Weeks within 10 Years
Purpose:– Test materials & Subcomponents– Demonstrate sustained fusion power
Features:– Based on recent GDT Results– Low Tritium Consumption,– No tritium Breeding Required– Simple Construction Geometry.