Transcript ARIES: Fusion Power Core and Power Cycle Engineering

ARIES: Fusion Power Core and Power
Cycle Engineering
The ARIES Team
Presented by A. René Raffray
ARIES Peer Review Meeting
University of California, San Diego
August 17, 2000
August 17, 2000
ARIES: Fusion Power Core and Power Cycle Engineering/ARR
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Presentation Outline
Approach Relies on:
– Detailed Analysis
Power Core and Power
Cycle Engineering:
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Power Cycle
Blanket
Divertor
Material
August 17, 2000
• Using up-to-date analysis tools
• Developing tools for specific analytical
needs
– Application of creative solutions to
extend design window
– Building Block
• build on previous ARIES design
experience in bettering the end product
– Community Interaction
• utilize national and international
community input in evolving material
properties and component parameters
• develop clear goals for R&D program
showing benefits
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Power Cycle: Quest for High Efficiency
Conventional
Steam Cycle:
Steel/Water
= 35%
ARIES-RS
Li/V
Supercritical
Rankine (water):
= 45%
ARIES-ST
FS/He/Pb-17Li
Brayton
(Low Temp. He):
> 45%
ARIES-AT
(SiC/SiC)/Pb-17Li
Brayton
(High Temp. He):
= 59%
T
• High efficiency translates in
lower COE and lower heat load
• Brayton cycle is best near-term
possibility of power conversion
with high efficiency
– Maximize potential gain from
high-temperature operation with
SiC/SiC
– Compatible with liquid metal
blanket through use of IHX
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1
2'
10
9
8
9'
2
5'
7'
6
PbLi Divertor +
Blanket Coolant
3
4
S
9
Intercooler 1 Intercooler 2
10
Recuperator
Intermediate
HX
3
Compressor 1
5
6
7
1
8
Wnet
Compressor 3
Compressor 2
Turbine
2
4
Heat
Rejection
HX
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Brayton Cycle Based on Near-Term Technology and
Advanced Recuperator Design Yields High Efficiency
Advanced Brayton cycle developed with
expert input from GA and FZK,
Karlsruhe
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FZK/UCSD ISFNT-4 paper, 1997
GA/UCSD ANS TOFE-14 paper, 2000
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Min. He Temp. in cycle (heat sink) = 35°C
3-stage compression with 2 inter-coolers
Turbine efficiency = 0.93
Compressor efficiency = 0.88
Recuperator effectiveness = 0.96
Cycle He fractional DP = 0.03
Total compression ratio set to optimize
system (= 2-3)
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High Efficiency Requires High Temperature
Operation
• Conventionally, maximum coolant temperature
is limited by structural material maximum
temperature limit
• Innovative design solutions in ARIES-ST and
ARIES-AT allow the blanket coolant exit
temperature to be higher than the structure
temperature
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ARIES-ST Utilizes a Dual Coolant Approach to Uncouple
Structure Temperature from Main Coolant Temperature
• ARIES-ST: Ferritic steel+Pb-17Li+He
• Flow lower temperature He (350-500°C)
to cool structure and higher
temperature Pb-17Li (480-800°C) for
flow through blanket
He-cooled Ferritic Steel
18
10
3.5
ARIES-ST
breeding
zone cell
SiC
232
Pb83Li17
18
250
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ARIES-AT Utilizes a 2-Pass Coolant Approach to
Uncouple Structure Temperature from Outlet
Coolant Temperature
• ARIES-AT: 2-pass Pb-17Li
flow, first pass to cool
SiC/SiC box and second pass
to “superheat” Pb-17Li
• Maintain blanket SiC/SiC
temperature (~1000°C) <
Pb-17Li outlet temperature
(~1100°C)
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Detailed Modeling and Analysis Required
to Demonstrate Blanket Performance
Multi-dimensional neutronics
analysis
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Latest data and code
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Tritium breeding requirement
influences blanket material
and configuration choices
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Blanket volumetric heat
generation profiles used for
thermal-hydraulic analyses
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Accommodation of Material Temperature Limits
Verified by Detailed Modeling
Moving Coordinate Analysis to Obtain Pb-17Li Temperature Distribution in
ARIES-AT First Wall Channel and Inner Channel under
MHD-Laminarization Effect
First Wall
Channel
vback
Pb-17Li
q''plasma
q''back
Inner
Channel
Poloidal
q'''LiPb
Radial
ARIES-AT Outboard
Blanket Segment
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vFW
SiC/SiC
First Wall
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Out
SiC/SiC Inner Wall
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Temperature Distribution in ARIES-AT Blanket
Based on Moving Coordinate Analysis
• Use plasma heat flux poloidal profile
• Use volumetric heat generation poloidal and
radial profiles
• Iterate for consistent boundary conditions for heat
flux between Pb-17Li inner channel zone and first
wall zone
• Calibration with ANSYS 2-D results
FW Max. CVD
and SiC/SiC
Temp. =
1009°C° and
996°C°
5.50
Average Neutron Wall Load = 3.19 MW/m2
5.00
Neutron Wall Load (MW/m2)
Max. SiC/PbLi Interf.
Temp. = 994 °C
Pb-17Li Outlet
Pb-17Li Inlet
Temp. = 1100 °C
Temp. = 764 °C
4.50
4.00
DIV.
3.50
3.00
2.50
2.00
1.50
OUTBOARD
INBOARD
1.00
0
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3 4 5 6 7 8 9 10 11 12 13 14 15
Poloidal Distance from Lower Outboard (m)
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Detailed Stress Analysis Using Latest Tool for
Maintaining Conservative Design Margins
Example of 2-D and 3-D Thermal and
Stress Analysis of ARIES-AT Blanket
Using ANSYS
Conservative SiC/SiC stress limit from Town Meeting:
Max. allowable thermal + pressure s = 190 MPa
Thermal Stress
Distribution in
Toroidal Half of
Outboard
Blanket Module
(Max. s =113
MPa)
August 17, 2000
Pressure
Stress
Analysis of
Inner Shell
of Blanket
Module
(Max. s
=116 MPa)
Pressure
Stress
Analysis of
Outer Shell
of Blanket
Module
(Max. s
=85 MPa)
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Develop Plausible Fabrication Procedure and
Minimize Joints in High Irradiation Region
Example Procedure for ARIES-AT
Blanket
1. Manufacture separate halves of the
SiCf/SiC poloidal module by SiCf
weaving and SiC Chemical Vapor
Infiltration (CVI) or polymer process;
2. Insert the free-floating inner separation
wall in each half module;
3. Braze the two half modules together
at the midplane;
Butt joint
Mortise and tenon joint
Lap joint
Tapered butt joint
Double lap joint
Tapered lap joint
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ARIES-AT Blanket Fabrication Procedure
Comprises:
1. Manufacturing separate halves of the
SiCf/SiC poloidal module by SiCf weaving and
SiC Chemical Vapor Infiltration (CVI) or
polymer process;
2. Inserting
the
free-floating
inner
separation wall in each half module;
3. Brazing the two half modules together at
the midplane;
4. Brazing the module end cap;
5. Forming a segment by brazing six
modules together (this is a bond which is
not in contact with the coolant); and
6. Brazing the annular manifold connections
to one end of the segment.
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Divertor Design Approach Relies on Community
Interaction and Innovative Solution to Maximize Performance
PFC and Physics Community
Interaction
– Tungsten as plasma-interactive
material
– ALPS liquid divertor option
collaboration
– Fully radiative divertor to maintain
reasonable peak heat fluxes, ~ 5
MW/m2
Divertor Coolant Compatible with
Blanket Coolant and/or Power Cycle
Fluid
– ARIES-RS: Li in insulated channel
(same coolant as blanket)
– ARIES-ST: He coolant (from power
cycle)+high heat flux porous media
(Pb-17Li as blanket coolant)
– ARIES-AT: Pb-17Li in SiC/SiC channel
(same coolant as blanket)
Provide Guidance
for R&D
e.g. MHD Effects for Liquid Metal
Cooled Divertor
– Minimize MHD effect by design
choice; use of coatings,
insulating inserts or SiC pipes
– However, solution must be
confirmed by R&D
August 17, 2000
• Assess Key Limiting Issue
• Detailed Analysis and Innovative
Solution to Maximize Performance of
Coolant/Material/Concept Combination
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ARIES-ST Divertor Designed for Thermal
Expansion Accommodation
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Tungsten Armor
High-temperature He coolant
Advanced high heat flux porous media
Several SBIR proposals based on similar
configuration
Initial high heat flux testing at Sandia
indicate high heat flux capability for this
material combination (~30 MW/m2)
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Moderate stresses in high heat flux region
High local stress at attachment, can be
relieved by flexible joint
1 mm
2 mm
ARIES-ST
Divertor Tube
Cross Section
3-D stress analysis
HOT
COLD
16 mm
3 mm
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MHD Effects Influence Both Pressure Drop and
Heat Transfer Even in Insulated Channels
MHD Accommodation Measure for ARIES-AT Divertor Design
• Minimize Interaction Parameter (<1) (Strong Inertial Effects)
• Flow in High Heat Flux Region Parallel to Magnetic Field (Toroidal)
• Minimize Flow Length and Residence Time
• Heat Transfer Analysis Based on MHD-Laminarized Flow
Pb-17Li Poloidal Flow in ARIES-AT
Divertor Header
Example schematic illustration
of 2-toroidal-pass scheme
for divertor cooling
Plasma q''
Poloidal
Direction
A
A
Cross-Section A-A
Toroidal
Direction
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Temperature Distribution in Outer Divertor PFC
Channel Assuming MHD-Laminarized Pb-17Li Flow
BT
PFC

LiPb LiPb
• Moving Coordinate Analysis
• Inlet Temperature = 653°C
• W Thickness = 3 mm
• SiC/SiC Thickness = 0.5 mm
• Pb-17Li Channel Thickness = 2 mm
• SiC/SiC Inner Wall Thick. = 0.5 mm
• Pb-17Li Velocity = 0.35 m/s
• Surface Heat Flux = 5 MW/m2
• Max. SiC/SiC Temp. = 1000°C
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Divertor Design Optimized for Stress Limit
Accommodation and Acceptable Coolant Pressure Drop
Example ARIES-AT Divertor Analysis
• For 2.5 mm tungsten, SiC/SiC pressure stress ~ 35 MPa
(combined SiC/SiC pressure +thermal stress ~ 190 MPa)
• DP is minimized to ~0.55 MPa
BT
PFC

LiPb LiPb
2.00
Inner Channel
Pressure Drop (MPa)
Orifice
PFC Channel
1.50
Total
1.00
0.50
0.00
0
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0.01
0.02
0.03
0.04
Toroidal Dimension of Divertor Channel (m)
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0.05
Close Interaction with International Material and
Blanket Design and R&D Communities
Combination of Low Activation Structural Material + Liquid Breeder Result in Attractive,
High Performance Blankets
– ARIES-RS: Li + Vanadium; ARIES-ST: Pb-17Li+FS+He; ARIES-AT: Pb-17Li+SiC/SiC
Recent Example of Interaction with International Material and Design Communities
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Organize International Town Meeting to bring together international (US, EU and Japan)
material and design SiC/SiC communities (ORNL, Jan 2000)
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Current material development and characterization status
Latest SiC/SiC-based blanket design: TAURO(EU), DREAM(Japan(), ARIES-AT( US)
Key SiC/SiC issues affecting blanket performance
Detailed info on website (http://aries.ucsd.edu/PUBLIC/SiCSiC/)
Town Meeting was very successful; achievements include:
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Develop list of properties and parameters for design study
Clear R&D need for high temperature high performance blanket
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Need better-quality material with reasonable thermal conductivity-stoichiometry goal
Temperature limit: Compability between Pb-17Li and SiC at high temperature
– Included in US R&D plan and being carried out in Europe
Paper deriving from meeting submitted to FE&D
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