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

Summary2

DEFINITIONS OF THE ARIES-ACT POWER CORE COMPONENTS

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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)

Question to ARIES edge plasma experts:Do the short inboard divertor slots work for your requirement?

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

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Plate Finger

q’’< 7 MW/m2 q’’> 7 MW/m2 (up to 13 MW/m2)

ARIES He-cooled W divertor design concepts:1.Finger, diameter=~20 mm, qallow=~13 MW/m2, ~0.55 million fingers for a power plant2.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 plant4.Finger-plate two zone concept

Cartridge with both slots and jets being combined Limit fingers to the zones with the highest heat flux

High heat flux regionLow heat flux region

pol.

tor.

rad.

BACKUP DESIGN OPTION OF THE ARIES-ACT POWER CORE

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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)

OVERALL LAYOUT AND INTEGRATION OF THE ARIES-ACT

POWER CORE

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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.

The saddle coil would be attached to the front of the inner door and removed together with the door during maintenance.

Cutting/Re-welding or Re-brazing the coolant lines are located inside of the VV.

Cutting/Re-welding or re-brazing line of access pipes

Cross section of the ACT power core

BACKUP OPTION OF THE LOCAL WATER-COOLED SHIELD

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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

CONFIGURATION OF THE VACUUM VESSEL

AND PORTS

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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.

Penetrations of access pipes

ARRANGEMENT OF THE COOLANT ACCESS PIPES CONNECTING TO

RING HEADERS

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Reference design

Other options discussed before

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

ARIES-AT like

ARIES-ACT CAD DRAWINGS ARE AVAILABLE

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http://aries.ucsd.edu/LIB/CAD/FIGURE/ARIES-ACT/

Schematic of the Pressure and Pressure Drops for the ARIES-ACT Blanket

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 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.

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ARIES-ACT SiC blankets

“Power core performance parameter (SCLL)” presented by Tillack at ARIES Group Meeting, 6 February

2012.

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

Configuration Definition, Dimensions and Composition of the IB Blanket

Inner module

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

FW, 2.0 cm 54.5% SiC45.5% LiPb

BW, 2.0 cm 54.5% SiC45.5% LiPb

Inner SW, 2.0 cm 54.5% SiC45.5% LiPb

Inner SW, 2.0 cm 54.5% SiC45.5% LiPb

BW, 2.0 cm 55.6% SiC44.4% LiPb

FW, 2.0 cm 55.5% SiC44.5% LiPb

Outer SW, 3.5 cm 81.3% SiC18.7% LiPb

FW

Inner module

Inner and Outer Modules(6 inner and 2 outer modules per

sector)

Outer module

35 cm

12Composition of the outer module:

Configuration Definition, Dimensions and Composition of the OB Blanket-I

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

Inner module

Outer module 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

FW, 2.0 cm 55.7% SiC44.3% LiPb

Inner SW, 2.0 cm 51.0% SiC49.0% LiPb

BW, 2.0 cm 53.8% SiC46.2% LiPb

FW, 2.0 cm 55.3% SiC44.7% LiPb

Inner SW, 2.0 cm 51.0% SiC49.0% LiPb

Outer SW, 3.0 cm 75.6% SiC24.4% LiPb

BW, 2.0 cm 55.3% SiC44.7% LiPb

Inner and Outer Modules(10 inner and 2 outer modules per sector)

First Wall

Inner module

Outer module

30 cm

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Composition of the outer module:

Configuration Definition, Dimensions and Composition of the OB Blanket-II

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

Inner module

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

FW, 2.4 cm 63.8% SiC36.2% LiPb

Inner FW, 2.4 cm 60.3% SiC39.7% LiPb

Outer BW, 3.9 cm 83.9% SiC16.1% LiPb

BW, 2.4 cm 63.6% SiC36.4% LiPb

FW, 2.4 cm 63.3% SiC36.7% LiPb

Inner SW, 2.4 cm 60.3% SiC39.7% LiPb

BW, 2.4 cm 63.0% SiC37.0% LiPb

Inner and Outer Modules(10 inner and 2 outer modules per sector)

45 cm

14Composition of the outer module:

Inner module

30 cm

Design limits: ~100 MPa for the primary stress (splitting from the total allowable stresses of 190 MPa)

Primary Stress of the IB Blanket

Maximum local stress is located at the 4 corners of ribs.

The stress in most regions of the FW, BW and SWs is less than ~50 MPa.

Firstwall

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Firstwall

Stress distribution of the outer module(Deformed shape scaled by 50 times)

The local primary stress occurs at the corners of the inner duct (~103 MPa) for a 2 cm thick side wall, and the stress at the most region is < 60 MPa.

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.

(Deformed displacement is scaled by 30)Total deformation=0.7 mm

Primary Stress Results of the OB Blanket-I

Firstwall

Firstwall

Primary stress of the OB-I

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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.

Pressure stress distribution of the OB-II

Primary Stress of the OB Blanket-II

Firstwall

Back wall

First wall

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Temperature Profiles of the IB for Thermal Stress*

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.

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.

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Thermal Stress Analysis in the Bottom Section of the Inboard Blanket

B.Cs: ͦ1.Free ͦexpansion, ͦand ͦallowing ͦfor ͦfree ͦbending2.Free ͦexpansion, ͦbending ͦsuppressed ͦat ͦthe ͦbottom ͦplanePressure ͦload: ͦ1.95 ͦMPa ͦat ͦannular ͦducts ͦand ͦ1.65 ͦMPa ͦat ͦthe ͦcenter ͦduct

Thermal stress distribution

Max. thermal stress =~91 MPaPressure stress<~50 MPaTotal stresses=~141 MPa

Thermal stress <60 MPaMax. pressure stress=~88 MPaTotal stresses=~148 MPa

19 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)

Thermal Stress Analysis in the Top Section of the Inboard Blanket

B.Cs: ͦ1.Free ͦexpansion, ͦand ͦallowing ͦfor ͦfree ͦbending2.Free ͦexpansion, ͦbending ͦsuppressedPressure ͦload: ͦ0.95 ͦMPa ͦat ͦthe ͦannualr ͦducts ͦand ͦ0.85 ͦMPa ͦat ͦthe ͦcenter ͦduct

Thermal stress distribution

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)

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Max. thermal stress =~118 MPaPressure stress<~24 MPaTotal stresses=~142 MPa

Max. pressure stress=~42 MPaThermal stress <52 MPaTotal stresses=~94 MPa

Max. thermal stress =~118 MPaPressure stress<~24 MPaTotal stresses=~142 MPa

Max. pressure stress=~42 MPaThermal stress <52 MPaTotal stresses=~94 MPa

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.