forschungszentrum karlsruhe fzk - euratom association 05/14/2005 thomas ihli 1 status of he-cooled...
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Forschungszentrum KarlsruheFZK - EURATOM ASSOCIATION
05/14/2005 Thomas Ihli
1
Status of He-cooled Divertor Design
Contributors: A.R. Raffray, and The ARIES Team
ARIES MeetingUniversity of Wisconsin, Madison
June 14-15, 2005
Presented by Thomas Ihli *
* Forschungszentrum Karlsruhe, currently exchange visitor to UCSD & The ARIES Team
Forschungszentrum KarlsruheFZK - EURATOM ASSOCIATION
05/14/2005 Thomas Ihli
2
Basic divertor concept
T-Tubes in parallel+ simplified manifold possible (more space)
+ reduced number of single parts
Caps in paralleltarget main structure:ODS ferritic steel
heat exchange part:tungsten alloy
+ single parts can be tested before assembly
Forschungszentrum KarlsruheFZK - EURATOM ASSOCIATION
05/14/2005 Thomas Ihli
3
Cooling concept jetarray 1300°C
armorcap
cartridgeMultijetMultijetMultijetMultijet
Slot JetSlot Jet + larger cooling area lower averaged heat transfer coefficient sufficient
Forschungszentrum KarlsruheFZK - EURATOM ASSOCIATION
05/14/2005 Thomas Ihli
4
Refined Design
Caps less curved reduced tube-tube distance
Reinforcement+
improved assemblyof tube and connector
Total unit length:90 mm for 10 MW/m2
better flow uniformity stronger parts
small deformation
25 mm
85 mm
D = 15 mm
Forschungszentrum KarlsruheFZK - EURATOM ASSOCIATION
05/14/2005 Thomas Ihli
5
Parts of T-Tube Design
Tube (W-Alloy)
Cartridge (Densimet 18)
Cap (W-Alloy)
Armor Layer (W)
T-connector (W-Alloy)
Transition piece (Slices from W to Steel)
Forschungszentrum KarlsruheFZK - EURATOM ASSOCIATION
05/14/2005 Thomas Ihli
6
Stress Intensities for basic geometry
acceptable total stress at flow channels
maximum of stress intensities(~ 360 MPa) within design limits
Forschungszentrum KarlsruheFZK - EURATOM ASSOCIATION
05/14/2005 Thomas Ihli
7
Shielding asymmetric heat load
tor.
rad.
12 MW/m2
0 MW/m2
Forschungszentrum KarlsruheFZK - EURATOM ASSOCIATION
05/14/2005 Thomas Ihli
8
Heat load on caps (by radiation)
Temperature peak(for more than 50 %load on tube ends)
stress intensities at tube end o.k.
Heat load attube end
100%
Heat load attube end
50%
Forschungszentrum KarlsruheFZK - EURATOM ASSOCIATION
05/14/2005 Thomas Ihli
9
0
5000
10000
15000
20000
25000
0 15 30 45 60 75 90
angle [deg]
h [
W/m
2 K]
slot width 0.6 mm
slot width 0.4 mm
slot width 0.5 mm
0
10000
20000
30000
40000
50000
60000
0 15 30 45 60 75 90
angle [degree]
h [
w/m
2K]
Heat transfer coefficientInfluence of
slot width
q’ = 20 MW/m2 G/A = 48 kg/m2
dp = 0.28 MPad = 7.5 mms = 0.25 mm q’ = 10 MW/m2
G/A = 24 kg/m2
dp = 0.11 MPad = 15 mms = 0.5 mm
q’ = 5 MW/m2
G/A = 12 kg/m2
dp = 0.027 MPad = 30 mms = 0.8 mm
Forschungszentrum KarlsruheFZK - EURATOM ASSOCIATION
05/14/2005 Thomas Ihli
10
0
5
10
15
20
25
30
35
40
45
50
0 5 10 15 20
heat flux (MW/m2)
tub
e d
iam
ete
r [m
m]
0%
5%
10%
15%
20%
25%
rel.
blo
we
r p
ow
er
[-]
tube diameter
relative blower power
Adjustment to various loads by scaling
q’ = 10 MW/m2 G/A = 24 kg/m2
dp = 0.11 MPad = 15 mms = 0.5 mm
d,b,l ~ 1/q’ G/A ~ q’P/Q’ ~ q’2
stressIntensities
~ const.
Forschungszentrum KarlsruheFZK - EURATOM ASSOCIATION
05/14/2005 Thomas Ihli
11
W – Fe transition
Tungsten
W-Fe Gradient Steel anchor
W-FE gradient transition:
Slices for stepwise adjustingof thermal expansion,
Brazed and/or HIPped
Forschungszentrum KarlsruheFZK - EURATOM ASSOCIATION
05/14/2005 Thomas Ihli
12
Schematic Divertor Module Design
T-Tubes (W)
Modulebody (Steel)pol.
rad.
600°C700°C
tor.
rad.wall cooling
manifold section
Co
llect
or
Co
llect
or
Forschungszentrum KarlsruheFZK - EURATOM ASSOCIATION
05/14/2005 Thomas Ihli
13
Divertor Module Design
T-Tubes (W)
Modulebody (Steel)
tor.
pol.rad.
Forschungszentrum KarlsruheFZK - EURATOM ASSOCIATION
05/14/2005 Thomas Ihli
14
Divertor Integration:
Divertor Target
Blanket Module
rad.
pol.
Independent Blanket/Divertor (if remaining breeding zone is still sufficient)
A1) Divertor Manifold box below Blanket module + Access to blanket pipes from below
same cutting/welding scheme for divertor + Simple shape for blanket
- Large cooled divertor manifold necessary - reduced breeding zone- divertor has to be disassembled from blanket
HT Shield with cut-outs for front access maintenance
X. Wang
X. Wang
Forschungszentrum KarlsruheFZK - EURATOM ASSOCIATION
05/14/2005 Thomas Ihli
15
Divertor Integration
Divertor Target
Blanket Module
rad.
pol.tor.
Independent Blanket/Divertor (if remaining breeding zone still sufficient)
A2) Divertor Manifold fits into cut-out in Blanket module + Divertor may be removed with Blanket + Access to blanket pipes from below+ Smaller divertor manifold
- Very complicated shape for blanket - Cooled divertor manifold necessary - Reduced shielding in manifold/tube area
HT Shield with cut-outs for front access maintenance
Forschungszentrum KarlsruheFZK - EURATOM ASSOCIATION
05/14/2005 Thomas Ihli
16
Divertor Integration Options
Divertor Target
Blanket Module
rad.
tor.pol.
OPTION B:
Divertor Manifold fits into cut-out in Blanket module + Independent Blanket/Divertor+ Less neutron heating for divertor manifold
- Complicated shape for blanket - Access of blanket pipes limited (tor.)- Divertor cannot be removed without the Blanket
HT Shield with cut-outs for front access maintenance
Forschungszentrum KarlsruheFZK - EURATOM ASSOCIATION
05/14/2005 Thomas Ihli
17
Divertor Integration Options
Divertor Target
Blanket Module
rad.
tor.pol.
OPTION C: Divertor Manifold in Blanket box
+ Lower neutron heating for divertor manifold+ No additional cooling for divertor manifold+ Thin manifold as included in blanket box+ Uncomplicated shape for blanket+ Better shielding than option A & B+ Access to blanket pipes from below
- Fix point at blanket back side - Divertor part of blanket
Slots between divertor channels at blanket box passage stress ok.
Forschungszentrum KarlsruheFZK - EURATOM ASSOCIATION
05/14/2005 Thomas Ihli
18
TOKAMAK Outboard target: cooling zones
Outboard
divertor power load685 MW
58 % neutron power42 % surface power
max. 80 % ofsurface poweron outboard 230 MW
0
1
2
3
4
5
6
7
8
9
10
0 0.5 1 1.5 2 2.5
target length [m]
he
at
flu
x [
MW
/m²]
< 4 MW/m²
< 2.5 MW/m²
≤ 10 MW/m²
L = 864 mm
L = 660 mm
L = 800 mm
Forschungszentrum KarlsruheFZK - EURATOM ASSOCIATION
05/14/2005 Thomas Ihli
19
43
1
2
OB
0
2
4
6
8
10
12
0 0.5 1 1.5 2 2.5
target length [m]
hea
t fl
ux
[MW
/m²]
600
620
640
660
680
700
720
tem
per
atu
re [
°C]
heat flux
T return channel
T supply channel = T_in finger
T_out finger
ZONE 1HHF
ZONE 2HHF
ZONE 3MHF
ZONE 4LHF
600°C
644°C
673°C
687°C 700°C
LAYOUT EXAMPLE TOKAMAK:thermo-hydraulic layout ΔT = 100 K
Forschungszentrum KarlsruheFZK - EURATOM ASSOCIATION
05/14/2005 Thomas Ihli
20
SUMMARY
Divertor Design Concept for ARIES CS has been developed
• New T-tube heat exchanger design • New manifold concept for rel. high neutron load (vol. heating)• Slot based jet impingement adapted• Good therohydraulic performance (Said & Regina FZK)• Thermal stress within design limits for 10 MW/m2
• Different Integration concepts can be chosen• Detailed target layout possible, when distribution data
available