progress and status of iter solid breeder test blanket ... · and status of iter solid breeder test...
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1
Progress
and Status of ITER Solid Breeder Test Blanket Module in China
Progress
and Status of ITER Solid Breeder Test Blanket Module in China
Presented By:
Kaiming Feng(Southwestern Institute of Physics, Chengdu, China)
Presented at 14th International Workshop on
Ceramic Breeder Blanket Interaction, Sep. 6-8, 2006, Petten, The Netherlands
2
Outline
I. Background
II. Progress and Status
III. R&D Plans
IV. Summary
3
Development and test different ideas of ITER-TBM, it should be one of the aims of the ITER Project.
China plans to develop own TBM concept for testing during ITER operation period based on China’s DEMO definition and development strategy.
The preliminary design and performance analysis of HC-SB TBM have been carried out. The final DDDshave been finished, moreover, related R&D plans are proposed.
I. I. Background
4
Two options of breeding blanket with ceramic and lead lithium-lead breeders might be chosen as China’s DEMO blanket concepts.
Selection of DEMO Blanket in China
HC-SB DEMO Blanket(SWIP) DFLL DEMO Blanket(ASIPP)
5
Selected HCSB-DEMO Parameters
Chinese HC-SB Demo ParametersFusion power/electric power, (MW) 2000 / ~ 600MWeMajor radius, (m) 7.0mMinor radius ,(m) 2.0-2.5mNeutron wall load ,(MW/m2) ~ 2.0Surface heating ,(MW/m2) ~0.3-0.5Tritium breeding ratio ,(TBR) >1.1Availability, (%) 50-70Divertor peak load, (MW.a/m2) 8.0 (water-cooled)Plasma operation mode Continuous
6
Basic Options on China TBM
Solid Breeder Blanket might be a basic option and first candidate in China. The lithium-lead breeding blanket is also recommendable concept.
We are also interested in other TBM concepts, such as, water-cooled solid breeder concept, etc.
China is proposing two TBM concepts (HCSB, DFLL) to be tested in one port, with a unified design of auxiliary systems.
7
II. Design ProgressII. Design Progress
of of CH CH HCHC--SB ITERSB ITER--TBMTBM
8
Originally Design of CH HC-SB TBM �2004 Version, ¼
Port,Integration design�
9
1-beryllium armor, 2-multiplier zone, 3-sidewall, 4-U-shaped shell, 5-cooling pipes, 6-breeder zone, 7-backplane, 8-He coolant(hot leg), 9-measure access, 10-attachment, 11-purged, 12-He coolant (cold leg)
Outline view for CH originally HCSB-TBM design
Be
SolidBreeder
Back-plane
He He
10
Modified Design of HC-SB TBM (2005 Version, 3x3 Modularization Design)
Configuration: BOT
Be armor:
2 mm
Max Temp. 514OC
First wall thickness:
30 mm
Material: LAFM
Max T: 506OC
Coolingtube:
18x14.5mm
Unit cells: 3X3 sub-modules
He pressure:
8 MPa
Configuration: BOT
Be armor:
2 mm
Max Temp. 514OC
First wall thickness:
30 mm
Material: LAFM
Max T: 506OC
Coolingtube:
18x14.5mm
Unit cells: 3X3 sub-modules
He pressure:
8 MPa
Modification Design of HCSB-TBM �2006, ½
Port, 3x6 Modularization Design�
Black-plate Design
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������
�������
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14
Connection of Components,gap
FW attachment
Cross-section of Sub-moduleGap structure
15
Assembly of HC-SB TBM in port frame
16
first wall grid sub-module backplate
support plate
Be pebble bed
Li4
SiO4
pebble bed
He supply pipe
He return pipe
purge gas supply pipe
purge gas return pipe
flexible support
shear key
3-D sketch map
17
Schematic views of Coolant flow
Coolant flow in the sub-module
Coolant flow in FW
Coolant Flow Direction
18
HCSB TBM integrated assembly (Common share the ancillary system)
19
HC-SB TBM Auxiliary System
HC-SB
TBMHC-SB
TBMHCS CPS
VV Port Cell TWCS vault
Tritium Building
BC
TES
TMS
NMS
20
HC-SB TBM Auxiliary Sub-system Design
21Flow scheme of the HCS system
HC-SB TBM
3 . 5 x2.5m2
Dust filter
Main HX
recuperator
Electric heater
Circulator
Valve
Draft layout of the helium cooling subsystem in the TCWS
TWCSHCSTBM
Helium Cooling System (HCS)
29
Neutron Measurement System (NMS)
Schematic diagram of neutron fluxes and spectra measurement system
micro-fission chamber
micro-fission chamber assembly 23Space Arrangement in TCWS for HCS subsystem
Space requirement:
A minimum net foot print area of 16 m2 in the TCWS vault, 0.5m3 in transfer cask, will be needed
Space requirement:
A minimum net foot print area of 16 m2 in the TCWS vault, 0.5m3 in transfer cask, will be needed
HCS TMS TES
CPS NMS TCWS27
Coolant Purification System (CPS)
1
3 a
4
6 a 6b
7a 7 b
8
£¹
He , 30 0 ¡æ
3 00 ¡æ
H e, 1 0M P a
5
E S
E S
3 b
1 0
H e
2 a2 b
Layout of the CPS
Flow chart of the CPS
2200
1500
1200
1£ -gas flow controller; 2a/2b£ -impurities getter bed; 3a/3b£ -tritium getter bed; 4£ -heater; 5£ -cooler; 6a/6b£ -buffer bank; 7a/7b£ -ionization chamber;
8£ -gas chromatograph9—circulator; 10—ZrCo bed
Space requirement:A space of 1500mm¡ Á1200mm¡ Á2200mm (L¡ ÁW¡ ÁH) is neededfor its assembly, maintenance and operation of the CPS.
26
Tritium Extraction Subsystem (TES)
4b
9 b
34 a
E S
6
7
8 a 8 b
9 a 1 0
1 1 a
1 2
E S
1 3 a
1 4 b
1 4 a
9 c
1 5H e
1 1 b
1 6
H2
T r i t i u m E x t r a c t i o n S y s t e m fo r T B M
1 3 b
1 3 c
4 c
1
2 a
2 b
1 T B M2 a /2 b F i l t e r3 C o o le r4 a /4 b / 4 c I o n i za t i o n C h a m b e r5 C o ld T ra p6 W at e r C o l l e c to r7 R ec u p e r a to r8 a /8 b M o le c u l a r S ie v e s9 a /9 b / 9 c B u ff e r1 0 H o t M g B e d1 1 a /1 1 b C o m p r e ss o r1 2 P d /A g P e r m e a te r1 3 a /1 3 b /1 3 c G e t t e r B e d1 4 a /1 4 b I SS1 5 H e a te r1 6 M a k e - u p U n i t
Ch e c k v av l eOp e n v a vl eCl o s ed va v l ePr e s su r e r e du c i n g v a v le
E S Ev a c ua t io n sy s t e m
¡À ¡À
¡À 5
V 1V 2
Flow chart of the TES sub-system Lay-out of the TES sub-system
Space Requirement:The TES system must be installed in a glove box.
The size of the Glove Box is: 5.5m¡ Á1.2m¡ Á5.5m (L¡ ÁW¡ ÁH).30
Tritium Measurement System (NMS)
The schematic of the gas flow calorimeter
Flow chart of the TMS
Layout of the TMS
21
Neutronics Measurement System (NMS)
Schematic diagram of neutron diagnostic system
micro-fission chamber
micro-fission chamber assembly
22
Tritium Measurement System (TMS)
Flow chart of the TMS The schematic of the gas flow calorimeter
23
Items NT-TBM EM-TBMConfiguration BOT (Breeder Out of Tube) Modules: 3×6 Sub-modules Modules: 3×6 Sub-modules
First wall areaNeutron wall loadingSurface heat flux
0.4844 m(W)×1.7600 m(H) 0.803 m2. 0.78 MW/m2
0.3 MW/m2
(normal condition)0.5 MW/m2
(extreme condition)
(Vertical). 0 0.1 MW/m2
(normal condition)0.3 MW/m2
(extreme condition)
Total heat deposition surface heat flux included 0.76 MW 0.177 MW
Globe TBR Lithium orthosilicate, Li4
SiO4 0.63 (3-D), 80% Li-6
Tritium production rate ITER operation condition 1.70 ×10-2
g/d
Sub-module dimension (P)×
(T) ×
(R) 253 mm×130mm×420 mm 253 mm×130mm×420 mm
Ceramic breeder
(Li4
SiO4
)One sizeThicknessMax. Temperature
Diameter: 1 mm, pebble bed90 mm (four zones)742 �
SiC
pebble bed, 01 mm
Neutron multiplier(Beryllium)
Two sizeThicknessMax. Temperature
Diameter: 0.5~1 mm, Pebble bed200 mm(five zones)613 �
Al pebble bed, 0.5~1 mm
Be armor ThicknessMax. Temperature
2mm550 �
2mm514 �
Structure Material Ferritic steelMax. Temperature
LAFM537 �
LAFM506 �
Coolant helium (He)
Pipes size
PressurePressure dropTemperature range (inlet/outlet)Mass flowDiameter (OD/ID)
8 MPa0.22 MPa300/500 �0.99 kg/s85/80 mm
8 MPa0.051 MPa 300/411 �0.62 kg/s85/80 mm
He purge flow (He) PressurePressure drop
0.12 MPa0.02 MPa
Design parameters for the HC-SB TBM
24
III. Performance Analysis III. Performance Analysis for HCSB ITERfor HCSB ITER--TBMTBM
25
3-D MCNP Model for Neutronics
Calculation
•planform
view
ITER side view 20o planform
view
TBM ITER side view planform
view
26
Performance Analysis for HC-SB TBM
Temperature distribution of FW Temperature distribution of sub-module
Stress distribution of FW Stress distribution of sub-module
Temperature on Flow Channel
The stress distribution
27
Safety Analysis of HCSB-TBM Design
36
Safety Analysis of CH HC-SB TBM (cont.)? activity and decay heat analysis
Total activity generated and contribution from each material
Total afterheat generated from each material
A total activity of 5.43×105 Ci is attained at shutdown with a contribution of 5.39¡ Á105Ci from the structure, 3.7×103Ci from the Li4SiO4.
At shutdown, the total decay heat is ~8.77¡ Á10-3 MW with a contribution of 8.71¡ Á10-3 MW and 6.36¡ Á10-5 MW from structure material and Li4SiO4, respectively.
38
Safety Analysis for CH HC-SB TBM (cont.)? LOCA and reliability analysis
Pressure transients from different models vs. time
Temperature changes of materials after the end of blow-down
LOCA analysis shows depressurization of the TBM helium coolant occurs within 10 to 15 s. Contribution to the pressure build-up in the VV is small (17.8 kPa). Tritium and activation products released from the TBM into the VV are insignificant compared to the total amount mobilized from non-TBM components. The TBM FW temperature can be kept, after the disruption burst has decayed variant to the reference case, with postulated unlimited steam access to the pebble beds, the estimated hydrogen production is the order of g only and the chemical heat is negligible.
Deformation Equivalent Stress
45
Safety Analysis for CH HC-SB EM-TBM (cont.)? Preliminary LOFA analysis for EM-TBM
e=0. 7
0
100
200
300
400
500
600
700
800
900
1000
0. 1 1 10 100 1000 10000 100000Ti me/ s
Temp
erat
ure/
o C
Fi r st Wal lBack Wal lHot t est Poi nt
e=0. 3
0
200
400
600
800
1000
1200
1400
0. 1 1 10 100 1000 10000 100000Ti me/ s
Temp
erat
ure/
o C
Fi r st Wal lBack Wal lHot t est Poi nt
Plasma no disruption: ex-vessel TBM coolant leaks
The two figures show temperature changes of materials after loss of flow accident. The smaller heat radiation emissivity of material is , the rapider temperatures of material increase. Under this accident condition, the auxiliary cool system is necessary to decrease the temperature of TBM shell.
44
Plasma disruption: in-vessel TBM coolant leaks
e=0. 7
0
100
200
300
400
500
600
700
0. 1 1 10 100 1000 10000 100000Ti me/ s
Temp
erat
ure/
o C
Fi r st Wal lBack Wal lHot t est Poi nt
e=0. 3
0
100
200
300
400
500
600
700
0. 1 1 10 100 1000 10000 100000Ti me/ s
Temp
erat
ure/
o C
Fi r st Wal lBack Wal lHot t est Poi nt
Safety Analysis for CH HC-SB EM-TBM (cont.)? Preliminary LOCA analysis for EM-TBM
This figure shows temperature changes of materials after the end of blow-down. When heat radiation emissivity of material is 0.7, the peaking value of FW is about 623 OC at the transient time of about 1s.
This figure shows temperature changes of materials after the end of blow-down. When heat radiation emissivity of material is 0.3, the peaking value of FW is about 623OC, too, at the transient time of about 1s. But curves have different change trends after 1000s.
Activation & afterheat Reliability
analysis E-M calculation model
E-M analyses LOCA analyses LOFA analyses
33
E-M Calculation Model
32
EM Analysis for the Centered Disruption
The maximum stresses components The maximum induced eddy currents The EM torque of the total TBM module
The distributions of the induced eddy currentsThe distributions of stresses in toroidal direction The distributions of shear stresses in radial and toroidal direction
28
Safety analysis /RELAP5 ApplicationSouthwestern I nstitute of Physics,China
ITER SWIP TBM GROUP
Piping hydrodynamic model Piping between HCS components
Southwestern I nstitute of Physics,China
ITER SWIP TBM GROUP
Be BeBe Be BeHe HeHe He He He He HeHe
Li4S
iO4
Li4S
iO4
Li4S
iO4
Li4S
iO4
radi al
pol oi dal
FW
Sub Module under modeled
Pipe
Model of main inlet manifold Model of First Wall(Poloidal-radial)
Model of intermediate manifolds
Southwestern I nstitute of Physics,China
ITER SWIP TBM GROUP
0 1 2 3 4 5 6 70
100
200
300
400
500
600
Pum
p ve
loci
ty(ra
d/s)
Time(s)
pump
0 2 4 6 8 10
0
5
10
15
20
Mas
s flo
w ra
te(K
g/s)
Time(s)
TBM inlet TBM outlet valve 201
5. Results of in-box LOCA for EM HCSB TBM
Pump velocity of in-box LOCA Mass flow rate of in-box LOCA
Southwestern I nstitute of Physics,China
ITER SWIP TBM GROUP
Temperature of Steady State Pressure of Steady State
0 20 40 60 80 100 120 140 160 180
100
150
200
250
300
350
400
450
Tem
pera
ture
(?)
Time(s)
Circulator FW outlet Sub module inlet TBM inlet TBM outlet
4. Results of Steady State EM HCSB TBM
0 20 40 60 80 100 120 140 160 1807.97x106
7.98x106
7.99x106
8.00x106
8.01x106
8.02x106
8.03x106
8.04x106
8.05x106
8.06x106
8.07x106
Pre
ssur
e(P
a)
Time(s)
Circulator FW outlet Sub module inlet TBM inlet TBM outlet
MCNPMCNP
3-D model3-D
modelSourcedata
Sourcedata
Nucleardata
Nucleardata
MC-FDKRMC-FDKR
FDKRFDKR
Decayγ
-sourceDecay
γ
-source
FDKR-MCFDKR-MC
INPUT DATAINPUT DATA
ACTIVATION & DECAY
DATA
ACTIVATION & DECAY
DATA
MCNP-
FDKR3-D Activation Calculation
Code
Decayγ
-sourceDecay
γ
-source
30
VI. R&D Plans on HCSB-TBMVI. R&D Plans on HCSB-TBM
31
Relevant R&D plansSystem Integration, Out-pile R&D• Module fabrication technology•
Thermo-mechanical integrity of module•
Thermo-mechanical performance•
Thermal hydraulic research
System Integration, Out-pile R&D• Module fabrication technology•
Thermo-mechanical integrity of module•
Thermo-mechanical performance•
Thermal hydraulic research
In-pile R&D
•
Breeder/multiplier development
•
Irradiation technology development
•
Irradiation tests of blanket partial mockup
In-pile R&D
•
Breeder/multiplier development
•
Irradiation technology development
•
Irradiation tests of blanket partial mockup
Tritium Recovery System Development
•
Process and system development
for hydrogen pump,
•
Coolant purification system
Tritium Recovery System Development
•
Process and system development
for hydrogen pump,
•
Coolant purification system
Neutronics
/ Tritium Production
Tests with 14MeV neutrons
•
Neutronics
performance of blanket
mockup and improvement of analysis accuracy
Neutronics
/ Tritium Production
Tests with 14MeV neutrons
•
Neutronics
performance of blanket
mockup and improvement of analysis accuracy
Material Development
•
Irradiation data of structure materials (CLAF), etc.
•
Environmental effect, etc.
Material Development
•
Irradiation data of structure materials (CLAF), etc.
•
Environmental effect, etc.
32
Development Strategy for the structural materials
Two sorts of structural materials will be focused on:-
RAFM for ITER-TBM and DEMO-TBM(1) Data base to support the design,(2) Goal: support the fabrication in future
-
Low activation V-based alloys(1) For advanced fusion reactor blanket concept(2) Basic study on mechanism
Budget (Total is about 4 M$)-
A small part is from the Nuclear Energy Project.-
Others will be supported by the MOST, as one of the projects in
ITER program.Collaborations
-
SWIP and ASIPP will be the leading institutes in China-
CIAE, IMR, NPIC and Universities will join. -
International, join IFMIF.
R&D of China RAFM �CLF-series�
(1) Chemical Composition, wt%
C Mn S P Cr Ni Mo V Nb Cu W O N Ta
CLF-1(F82)
0.037 0.10 0.0006 0.0041 8.32 0.023 0.009 0.16 0.02 <0.02 - 0.001
60.00
2-
CLF-2(Eurofer97)
0.025 0.28 0.0006 0.0040 8.69 - - 0.18 - <0.02 1.11 0.005 0.00
20.10
(2) Mechanical propertyType Tensile strength
σb (MPa)Yield strengthσ0.2 (MPa)
Tensile ductilityδ
(%)Impact ductility, Ak
(J/cm2)
CLF-1 (~15%CW) 495.0 365.0 33.2 >300
CLF-2 (~15%CW) 528.3 435.0 25.8 >300
34
Development of Neutron Multiplier(Be)
Main Chemical Composition of CH 2# and US S-65C**
China has also large yielding capacity of Be and relevant experiences of neutron multiplier.China has built Be fabrication and manufactory in Ningxia Orient Non-ferrous Metal Group Co. A new project, to develop high quality Be in China, is being implemented for ITER project.
Type No. Elements (wt.%)Be BeO Fe C Al Mg
Grade 2# (CH) 99 0.80 0.05 - 0.075 0.015
S-65C VHP (US) 99 1.0 0.08 0.1 0.060 0.060
35
Solid Breeder TechnologyChina has studied tritium-processing technology supported by
national fusion program for many years. Knowledge accumulated in
this field is useful for the TBM tritium technology.
Two kinds of ceramic breeder( Li4
SiO4 , Li2
TiO3
), are developing in China.
Fabrication sample of the Li4
SiO4
pebblesFabrication of the ceramic powder
36
Fabrication
and Experiment of Ceramic Pebbles***
Diameter: 1~5mmRelative density:60~80%T.D.Crushing load:30~70N
Diameter: 1~5mmRelative density: 60~80%T.D.Crushing load: 30~70N
γ-
LiAlO2
Li2
ZrO3
Li4
SiO4
Diameter: 1mmRelative density: 90%T.D.
***Contribution from CAEP
37
Irradiation Test on High Flux Reactors
China has built a High Flux Engineering Test Reactor
(HFETR) in the China Institute of Nuclear Power (CINP) . HFETR is a largest one in Asia.
Neutron Flux: Thermal neutrons :
6.2×1014
n/cm2•sec; (E<0.625eV)Fast neutrons :
1.7 ×1015
n/cm2•sec; (E>0.625eV)235U of 90% enriched in U fuel.
Total power: 125 MW (th)
In addition, there are two sets experiment reactors with power of 20MW and 40MW are constructing in CIAE and CAEP of China.
These facilities and their ability are useful for the irradiation experiment of the TBM structure materials, tritium breeders, neutron multiplier etc. High Flux Engineering Test Reactor
(HFETR)
38
Measurement and control system
Optical pyrometer(300-3000 �)
CCD View Electron-gun and pump system
Main parameters:•
Pressure: 1-2×10-3
Pa (e-
gun chamber), 2-4 ×10-3
Pa (main chamber).•
Power: max. 3kW (60kV, 50mA).•
E-beam: Gaussian distribution, max. spot: ~φ20mm (ellipse).
High Heat Flux Tests
39
HIP Technology development
Cu/SS +SS tubes, 80x240
850oC/120MPa/3hr
The technology is based on drilling holes and HIPing.
Tensile strength is more than 260MPa.
CuCrZr/316L-HIP weld module
Supersonic wave detector
1. NDT method for flat interface of Cu-SS
2. NDT method for the interface of Cu-SS tube
40
High Temperature He Experiment Loop
High Temperature He Experiment Loop
A High Temperature He Experiment Loop
(HTHEL)with 700 OC and 8-
10 MPa, which is useful for HC-SB TBM design and R&D activities, is proposed to be built in SWIP.
He Test Loop for HTGRTemp.: 900 OC, Total Power: 10MW Pressure: 3 MPa
41
Proposed test facilities prior to TBMs installation in ITER
Facilities name Main objectives Parameters Location
A high temperature He Experiment Loop based on China HTGR technologies.
TBM mock-ups test 500-700 OC and 8-10 MPa
(adjustable)SWIP/ Under construction
A facility for high heat flux properties test
Evaluation of plasma
facing materials and
components
Max. power density: 20 MW/m2,Active cooling, control of the temperature of coolant from RT-
150
SWIP/ Under construction
High Flux Engineering Test Reactor (HFETR)
Materials Test Thermal neutrons : 6.2×1014
n/cm2•sec; (E<0.625eV)Fast neutrons : 1.7 ×1015
n/cm2•sec; (E>0.625eV)
CINP/ (existing)
Facilities of tritium extraction, purification, permeation , and test
Tritium extraction and recovery experiment from the purge gas
and coolant.
TBD CAEP,CIAE & SWIP (planning)
Tritium technologies-
Tritium extraction & purification-
Tritium control and ISS-
Tritium loop qualification-
Tritium permeation barriersCeramic breeder technologies
-
Fabrication; -
Performance test;-
Simulation and modeling;-
Irradiation test.Thermo-mechanics and helium flow testTest of on the pebble bed thermo-mechanics and helium flow
stability and distribution by means of a high temperature, high pressure He test loop.
Expected Collaboration on R&D
43
IV. SummaryIV. SummarySolid Breeder Blanket should be the basic option and first candidate in China. The progress and status of CH HC-SB TBM since 2004 are introduced briefly.
Under the cooperation with domestic institutes, a update designdescription document (DDD) have been completed. The preliminary safety analysis reports will be submitted by the end of this year.
Preliminary R&D program as well as the collaboration expected with other Parties are presented.
Some key technologies are to be implemented, such as high temperature He experimental loop, Low-activation material (CLF), high qualified beryllium, HIP welding technology, optimized lithium ceramic breeder, etc.
Relevant R&D on the key techniques are being preformed intensively and systematically with the cooperation of domestic and international institutions and companies.
44
Thank you for your attention!
4521th IAEA FEC Conference will be hold in
Chengdu International Conference Center, Oct.16-20, 2006