UPDATED ARIES-ACT
POWER CORE DEFINITION
AND SIC BLANKET
X.R. Wang, M. S. Tillack, S. Malang
F. Najmabadi and L.A. El-Guebaly
ARIES-Pathways Project Meeting
Gaithersburg, MD
May 30-June 1, 2012
OUTLINE

Updates on the overall layout and integration of the ARIES-ACT
power core configuration

Definition of the power core components based on new radial
builds



blankets, divertors, structural ring, VV and LT shield

Locations of the control coils and saddle coil

Layout of the LiPb and He access pipes connecting to the sector
and ring headers

Size and location of the vacuum pumping ducts
Updates on the SCLL blanket design and optimization

Internal details, such as the parameters, dimensions of the IB
and the OB blankets

Primary and thermal stresses of the last iteration
Summary
2
DEFINITIONS OF THE ARIES-ACT POWER
CORE COMPONENTS
 Inboard blanket


straight from bottom to top and LiPb running behind
and above the upper divertor
manifold feeding the LiPb to the IB blanket from bottom
behind the divertor structure
 Outboard blanket-I and II


4 cm stabilizing shells attached to the OB-II at the top &
bottom, and 1 cm kink shell in the middle
LiPb manifolds at the bottom
 Top and bottom divertor target and
structure



shorter inboard divertor slots (comparing to ARIES-AT)
Helium cooled two zone W divertor design concept
Finger for q>7 MW/m2, flat-type plate for q<7 MW/m2
 Structural ring




a closed ring in poloidal direction will provide enough
mechanical strength to support the blankets and
divertors
all the inboard/outboard blankets upper and lower
divertor are attached to the structural ring by bolts or
mechanical keys to form a closed unit (replacement unit)
the replacement unit is supported at bottom through the
VV and LW shield
the entire unit is free expansion in all directions
Replacement unit (1/16)
3
Question to ARIES edge plasma experts:
Do the short inboard divertor slots work for your requirement?
TWO-ZONE DIVERTOR CONCEPT CAN
BE APPLIED IN THE ARIES-ACT
Plate
Low heat flux region
q’’< 7 MW/m2
Finger
High heat flux region
q’’> 7 MW/m2 (up to 13 MW/m2)
rad.
tor.
pol.
ARIES He-cooled W divertor design concepts:
1. Finger, diameter=~20 mm, qallow=~13 MW/m2, ~0.55 million fingers for a power plant
2. T-Tube, diameter=~15 mm, tube length= ~10 cm, qallow=~11 MW/m2
3. Plate, 20 cm(tor.) x 100 cm (pol.), qallow=~9 MW/m2, ~750 plate units for a power plant
4
4. Finger-plate two zone concept


Cartridge with both slots and jets being combined
Limit fingers to the zones with the highest heat flux
BACKUP DESIGN OPTION OF THE ARIESACT POWER CORE
 Inboard blanket
 straight from bottom to top divertor region,
but no LiPb running behind and above the
upper diveror
 being tapered from 35 cm to 20 cm at the
bottom divertor region
 Top and bottom divertor regions
 slightly longer inboard divertor slots
(comparing to the reference design)
 an additional helium-cool steel shielding
required at the upper divertor region
(between structural ring and divertor
structure)
 Structural ring
 being tapered from 20 cm to 15 cm at the
inboard divertor region
1/16 Replacement unit
(backup design option)
5
OVERALL LAYOUT AND INTEGRATION OF
THE ARIES-ACT POWER CORE
 The VV will be a webbed-structure cooled by
He and will be run hot (~300-500 ͦC) to
minimize tritium migration to the VV. In the
CAD drawings:



~5 cm at inboard
~10 cm at top, bottom and outboard
~10 cm for the port walls
 Low temperature shield is cooled by water
and run at room temperature.
 The size and locations of pumping ducts will
be the same as the ARIES-AT.
 Control coils are supported by the structural
ring and be capable of removing to upper
during the maintenance.
 There is only ~5 cm space for local shield
between outboard TF legs and port side walls,
therefore, an inner door on the VV will be
required for protecting the coils, and the door
can be cooled by helium.
Cross section of the ACT power core
Cutting/Re-welding or rebrazing line of access pipes
 The saddle coil would be attached to the front
of the inner door and removed together with
6
the door during maintenance.
 Cutting/Re-welding or Re-brazing the coolant
lines are located inside of the VV.
BACKUP OPTION OF THE LOCAL WATERCOOLED SHIELD
 There is only one door at the end of the
maintenance port.
 The saddle coils are attached to the back of
the structural ring and needs to be removed
through the port before removing the control
coils during the maintenance.
 The TF coils have to be enlarged in order to
increase the space between the outboard TF
legs and the port side walls.
~5 cm space for
local shield
7
CONFIGURATION OF THE VACUUM VESSEL
AND PORTS
Penetrations of
access pipes
1 sector
12 sectors
 The VV will be designed as the webbed-structure cooled by the helium,
including the VV, port and the outer door (Farrokh’s talk).
 The geometry definition is based on maintenance requirements,
integration of the overall power core and primary stress iterations.
8
ARRANGEMENT OF THE COOLANT ACCESS
PIPES CONNECTING TO RING HEADERS
Other
options
discussed
before
ARIES-AT like
Reference design
 There are 7 concentric assess pipes with cold coolant
in the annular and hot in the center
 3 LiPb access pipes for the blankets
 2 He access pipes for the upper and lower divertors
 2 He access pipes for the structural ring
9
ARIES-ACT CAD DRAWINGS ARE
AVAILABLE
10
http://aries.ucsd.edu/LIB/CAD/FIGURE/ARIES-ACT/
Schematic of the Pressure and Pressure Drops
for the ARIES-ACT Blanket
“Power core performance parameter (SCLL)” presented by Tillack at ARIES Group Meeting, 6 February 2012.
ARIES-ACT
SiC blankets
 The results indicate that the pressure and pressure drops of the ARIES-AT blanket were
underestimated (~1 MPa at the inlet and 0.75 MPa at the exit).
 The configurations, parameters and dimensions of the IB&OB blankets need to be designed to 11
accommodate the pressure of ~2 MPa and meet the stress limits (~190 MPa for the combined
primary and thermal stresses)
 Design iterations and optimizations have been performed based on primary stress limits and
the volume fraction of the SiC.
Configuration Definition, Dimensions and
Composition of the IB Blanket
Inner module







Total number of the modules per sector=8 (6 inner modules
and 2 outer modules)
The fluid thickness in the FW, SW and BW annular=10 mm
(4 mm for the ARIES-AT)
The number of the sub-ducts=18 (21 for the ARIES-AT)
Wall thickness of the outer and inner ducts= 5 mm
Thickness of the front and back ribs=4 mm (2 mm for the
ARIES-AT)
Thickness of the ribs at the two sides with pressure balance=
2 mm
Diameter of the curvature for the FW and BW, 35 cm
FW, 2.0 cm
54.5% SiC
45.5% LiPb
BW, 2.0 cm
54.5% SiC
45.5% LiPb
Inner
module
35 cm
FW
Outer
module
Inner SW, 2.0 cm
54.5% SiC
45.5% LiPb
Outer module
 Increase the number of the ribs from 4 to 10
 Increase the rib thickness from 2 mm to 4 mm at the outer side
 Increase the thickness of the outer SW from 5 to 20 mm
Inner and Outer Modules
(6 inner and 2 outer modules per sector)
Composition of the outer module:
FW, 2.0 cm
55.5% SiC
44.5% LiPb
BW, 2.0 cm
55.6% SiC
44.4% LiPb
Inner SW, 2.0 cm
54.5% SiC
45.5% LiPb
12
Outer SW, 3.5 cm
81.3% SiC
18.7% LiPb
Configuration Definition, Dimensions and
Composition of the OB Blanket-I
Inner module







Inner
module
Total number of the module for each OB blanket sector=12 (10 inner
modules and 2 outer modules)
Total number of the sub-ducts=18 (23 for the Old OB-I, 4 in the
front, 13 at the back and 6 at the sides)
The wall thickness of the outer/inner ducts=5 mm
The fluid thickness in the annular= 10 mm (4 mm for the Old OB-I)
Rib thickness in the front and back=4 mm (2mm for the Old OB-I)
Rib thickness on both sides=2 mm
Diameter of the curvature for the FW and BW=30 cm
FW, 2.0 cm
55.7% SiC
44.3% LiPb
BW, 2.0 cm
53.8% SiC
46.2% LiPb
Inner SW, 2.0 cm
51.0% SiC
49.0% LiPb
Outer module



30 cm
Outer
module
First Wall
Increase the thickness of the outer SW from 5 to ~15 mm
Increase the numbers of the rib from 2 to 5
Increase the thickness of the outer SW ribs from 2 to 4 mm
Inner and Outer Modules
Composition of the outer module:
FW, 2.0 cm
55.3% SiC
44.7% LiPb
BW, 2.0 cm
55.3% SiC
44.7% LiPb
Inner SW, 2.0 cm
51.0% SiC
49.0% LiPb
(10 inner and 2 outer modules per sector)
Outer SW, 3.0 cm
75.6% SiC
24.4% LiPb
13
Configuration Definition, Dimensions and
Composition of the OB Blanket-II
Inner module
Inner module







45 cm
Total number of the module for each blanket sector=12 (10
inner modules and 2 outer modules)
Total number of the sub-ducts=24 (20 for the Old OB-II)
The wall thickness of the outer/inner ducts=7 mm
Rib thickness at 4 corners=6 mm (4 mm for the Old OB-II)
Rib thickness on both sides=2 mm
The fluid thickness at the annular=10 mm (8 mm for the Old
OB-II)
Diameter of the curvature for the FW and back wall=45 cm
FW, 2.4 cm
63.3% SiC
36.7% LiPb
BW, 2.4 cm
63.0% SiC
37.0% LiPb
30 cm
Inner SW, 2.4 cm
60.3% SiC
39.7% LiPb
Outer module



Increase the thickness of the outer SW from 5 to 22 mm
Increase the thickness of the rib at the outer SW from 2 to 6
mm
Increase the numbers of the rib at the outer SW from 5 to 9
Inner and Outer Modules
(10 inner and 2 outer modules per sector)
Composition of the outer module:
FW, 2.4 cm
63.8% SiC
36.2% LiPb
BW, 2.4 cm
63.6% SiC
36.4% LiPb
Inner FW, 2.4 cm
60.3% SiC
39.7% LiPb
14
Outer BW, 3.9 cm
83.9% SiC
16.1% LiPb
Primary Stress of the IB Blanket
First
wall
First
wall
Stress distribution of the outer module
(Deformed shape scaled by 50 times)
Design limits: ~100 MPa for the primary stress  The local primary stress occurs at the corners of
the inner duct (~103 MPa) for a 2 cm thick side
(splitting from the total allowable stresses of 190
wall, and the stress at the most region is < 60
MPa)
MPa.
 Maximum local stress is located at the 4 corners
15
of ribs.
 The stress in most regions of the FW, BW and
SWs is less than ~50 MPa.
Primary Stress Results of the OB Blanket-I
First
wall
Primary stress of the OB-I
First
wall
(Deformed displacement is scaled by 30)
Total deformation=0.7 mm
 Maximum local stress is located at the corners of ribs and
it is ~71 MPa.
 The stress in most regions of the FW, BW and SWs is less
than ~55 MPa.
16
Primary Stress of the OB Blanket-II
Back wall
First
wall
First wall
Pressure stress distribution of the OB-II
 Maximum local stress is located at the 4 corners of the
inner duct, it is ~80 MPa.
 The stress in most regions of the FW, BW and SWs is less
than ~53 MPa.
 Maximum total deformation is ~0.8 mm.
17
Temperature Profiles of the IB for
Thermal Stress*
surface
central coolant 1
back coolant 2
1000
1100
1050
FW coolant 1
central coolant 2
back wall
FW coolant 2
back coolant 1
950
1000
900
950
850
900
850
800
800
bottom
middle
top
750
750
700
700
0
20
40
60
80
Node number
100
120
0.0
1.0
2.0
3.0
4.0
5.0
Axial distance (m)
 Max. temperature of the SiC is ~960 ͦC(allowable SiC temperature <1000 ͦC ) and
max. LiPb temperature is ~1100 ͦC.
 Front-to-back module temperature differences are modest, ~100 ͦC at the bottom and
~130 ͦC at the top.
18
 Thermal stresses at both bottom and top sections will be calculated.
* “Power core performance parameter (SCLL)” presented by Tillack at ARIES Group Meeting, 6 February 2012.
Thermal Stress Analysis in the Bottom Section of the
Inboard Blanket
Max. thermal stress =~91 MPa
Pressure stress<~50 MPa
Total stresses=~141 MPa
Thermal stress <60 MPa
Max. pressure stress=~88 MPa
Total stresses=~148 MPa
Thermal stress distribution
B.Cs:
1. Free expansion, and allowing for free bending
2. Free expansion, bending suppressed at the bottom plane
Pressure load: 1.95 MPa at annular ducts and 1.65 MPa at the center duct
 Max. combined primary and thermal stresses are ~141 MPa for the B.C 1, and
~178 MPa for the B.C. 2 (allowable stress=190 MPa)
19
Thermal Stress Analysis in the Top Section of the
Inboard Blanket
Max. thermal stress =~118 MPa
Pressure stress<~24 MPa
Total stresses=~142 MPa
Max. thermal stress =~118 MPa
Pressure stress<~24 MPa
Total stresses=~142 MPa
Max. pressure stress=~42 MPa
Thermal stress <52 MPa
Total stresses=~94 MPa
Max. pressure stress=~42 MPa
Thermal stress <52 MPa
Total stresses=~94 MPa
Thermal stress distribution
B.Cs:
1. Free expansion, and allowing for free bending
2. Free expansion, bending suppressed
Pressure load: 0.95 MPa at the annualr ducts and 0.85 MPa at the center duct
 Max. combined primary and thermal stresses are ~142 MPa for the B.C 1, and
~182 MPa for the B.C. 2 (allowable stress=190 MPa)
20
SUMMARY
 The overall power configuration and integration of the ARIES-ACT power core have
been updated to new radial builds. The working CAD drawings are now available at
ARIES web site:
http://aries.ucsd.edu/LIB/CAD/FIGURE/ARIES-ACT/
 The parameters of the SiC/LiPb blankets, including the size of the module, the
numbers of the modules per sector, FW curvatures, wall thickness, rib thickness and
rib spacing have been re-defined and optimized based on the primary stresses and the
SiC volume fraction.
 Thermal stress analysis of the inboard blanket has been performed and the results
indicate that the stress limits are satisfied.