Current Status of Solid Breeder TBM in China Presented at CBBI-16 meeting Sep. 8 -10, 2011, Red Lion on the River, Portland, OR, USA Presented by: Kaiming.
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Current Status of Solid Breeder TBM in ChinaCurrent Status of Solid Breeder TBM in China
Presented at CBBI-16 meeting
Sep. 8 -10, 2011, Red Lion on the River , Portland, OR, USA
Presented by: Kaiming Feng
(On behalf of Chinese HCCB TBM Team)
Co-Institutes:1). China Academy of Engineering Physics (CAEP), Mianyang, P.R. China 2). Chinese Institute of Atomic Energy (CIAE) , Beijing, 100084, P.R. China.3). Chinese Institute of Nuclear Power ( CINP), Chengdu 610043, P.R. China4). Shanghai Ceramic Institute, Chinese Academy of Science (SCICAS), P.R. China
OUTLINEOUTLINE
11. Introduction
2. Progress on Updated Design
3. Progress on Relevant R&D
4. Test Plan and Cooperation
5. Summary
1. Introduction1. Introduction
ITER is an unique opportunity to test tritium breeding blanket mock-ups in an integrated tokamak operating conditions;
Helium-cooled ceramic breeder (HCCB) test blanket module will be the primary option of the Chinese ITER TBM program;
China has the position of Port Master (PM) in port number 2 and is leading the HCCB concept as the TBM Leader (TL). CN HCCB TBM will be tested at different phases of ITER operation;
In order to reduce the effects of magnetic field ripple, the TBM design was updated with reduced RAFM mass;
Related R&D on key components, materials, fabrication and mock-up test have being implemented in China.
It was assumed that DEMO is a next step after ITER. DEMO will demonstrate the integration technology, materials, economics, safety, and
environment for the fusion energy applications. TBM testing on ITER is an important approach toward to DEMO.
Roadmap to DEMORoadmap to DEMO
HL-2A
ITER
DEMO
Power Plant
Fusion Breeder?
ITER -TBM
IFMIF
2020 2035 20502010
EAST
CTF? FNST?
5
As one options of breeding blanket with the Helium-cooled solid breeders/RAFM steel (HCSB-DEMO) will be chosen as China’s DEMO blanket concepts.
HCCB TBM will demonstrate the functions required for Chinese HCSB-DEMO blanket under at ITER operation condition.
HCSB-DEMO Blanket ConceptHCSB-DEMO Blanket Concept
HC-SB DEMO Blanket
3-D View of HCSB DEMO blanket
.K.M.Feng, et.al., J. Fusion Eng.& Desgn, 84(2009)2109-2113.
TBM Concepts and Port-Sharing
Six TBM Systems to be installed in ITER in different operation phases
Port No. and PM TBM Concept TBM Concept
A (PM : EU) HCLL (TL : EU) HCPB (TL : EU)
B (PM : JA) WCCB (TL : JA) PMG: US/KO, LLCB? TL?
C (PM : CN) HCCB (TL : CN) LLCB (TL : IN)
PM : Port Master, TL : TBM Leader
HCLL : Helium-cooled Lithium Lead HCPB : He-cooled Pebble Beds (Ceramic/Beryllium)
WCCB : Water-cooled Ceramic Breeder (+Beryllium) HCCB : He-cooled Ceramic Breeder (+Beryllium) LLCB : Lithium-Lead Ceramic Breeder (LiPb & He, Dual-Coolant type)
CN HCCB TBM will demonstrate the functions required for Chinese DEMO blanket in ITER condition
HCSB-DEMOITER cross-section
CN HCCB TBM
Relationship of ITER,TBM and DEMO
7
A series of the Chinese HCCB TBM design have been carried-out since 2004 within the space limitation and technical requirements specified by ITER.
2. Progress on CN HCCB TBM Design2. Progress on CN HCCB TBM Design
Outline of HCCB TBM Design
- TBM structure: Sub-module arrangement- Structure material: RAFM (CLF-1);- Tritium breeder: Li4SiO4 pebble bed, 80%Li-6 ;- Neutron multiplier: Be pebbles bed;- Coolant and purge gas: Helium gas - Coolant pressure: 8MPa- Coolant temperature: 300 OC(inlet) -500 OC (outlet)- Tritium production ratio (TPR): 0.0505g/d
Integration View of CN HCSB TBM
Cross-section of SB
Assembly scheme of Sub-Modules
Basic design characteristics:
Originally design of CN HCCB TBM have been completed before 2009.
9
Updated Design of HCCB TBM for Reduction RAFM Mass
HCCB TBM Module TBM Sub-module arrangement Cross-section of SM
- The RAFM mass is reduced from 2.3t to 1.6t).
- TPR is increased by factor from 0.051g/day to 0.0798g/day.
Objectives of updated design:
- to simplify Sub-module structure;
- to reduce RAFM mass;
- to improve TPR performance;
Exploded view of sub-module
Main modification
An optimized all RAFM design with reduced mass of 1.3t is on going. A updated DDD report will be completed soon.
Results shown:
- Reduce radial dimension of the FW and sub-modules.- Bypass is introduced to TBM design to control the difference of
flow-rates .
- Arrangement of pebble beds in the sub-module is changed from the former transverse direction to the current vertical direction.
10
Performance Analyses for Updated TBM Design
a) RAFM material b) Be pebble bed c) Li4SiO4 pebble bed
ParametersPrevious design
Updated design
RAFM mass, ton 2.31 1.63
Tritium Production Rate (TPR), (g/d)
0.051 0.079
Peak power density (MW/m3)
6.26 6.82
Total power deposit (MW)
0.587 0.642
Tmax= 517 OCTmax= 548 OC Tmax= 621 OC
Temperature and stress distribution of FW
Temperature Distribution of Sub-module
Main parameters meet design requirement. TPR is obviously increased.
Main calculation results
d)Sub-module
thermal analysis model
RAFMs (CLF-1)
Li4SiO4
pebble bed
Be pebble bed
Thermal conductivity [W/(m·K)]
29.8(400
) ℃
1.0-1.2 (500-900 ℃)
5.4, 8.8, 10.6 (500, 600, 700
)℃
Max. allowable temperature [ ]℃
550 920 700
Thermal analysis results of sub-module
Primary stress Secondary stress
Stress analysis
Thermal analysis
Performance Analyses for Updated TBM Design
13
CN HCCB TBM Auxiliary Sub-system Design
Basic configuration BOT (Breeder Out of Tube) Modules: 2×6 Sub-modules
First wall area
Neutron wall loading
Surface heat flux
0.484 m(W)×1.660 m(H) 0.803 m2.
0.78 MW/m2
0.3 MW/m2 (normal condition)
0.5 MW/m2 (extreme condition)
Total heat deposition NT-TBM PI-TBM 0.642 MW
Tritium production rate ITER operation condition 0.079g/FPD
TBM module dimension (P)× (T) × (R) 1660mm×484mm×675mm
Ceramic breeder (Li4SiO4) Single size
Thickness
Max. Temperature
D = mm, pebble bed
90 mm (four zones)
699℃
Neutron multiplier
(Beryllium)
Two size
Thickness
Max. Temperature
Diameter: 0.5~1 mm, Pebble bed
200 mm (five zones)
537℃
Structure Material Ferritic steel
Max. Temperature
CLF-1
538 ℃
Coolant helium (He)
Pipes size
Pressure
Pressure drop
Temperature range (inlet/outlet)
Mass flow
Diameter (OD/ID)
8 MPa
0.08 MPa
300/500 ℃1.36kg/s
101.6/85.5 mm
He purge flow (He) Pressure
Pressure drop
Mass Flow
Diameter (OD/ID)
0.12 MPa
0.02 MPa
0.6 g/s
35/30 mm
Design Parameters for the HCCB TBMDesign Parameters for the HCCB TBM
CN TBS Integration with ITER (Con’t)CN TBS Integration with ITER (Con’t)
C5CN-HCCB
C6IN-LLCB
15
2 half-ports
View of Pipe Forest and TBM-Sets in Port #2
16
Port Cell area
Tokamak Coolant Water System vault
L2 of Tritium building for TES
Interface 1 Interface 2a Interface 2bInterface 3
India part
China part
Port 2#(Port Plug)
Interspace(Pipe forest)
Port Cell(AEU)
Space reserved for CN TBS has been identified. Arrangements of CN TBS have been considered. Investigation of components which selected for CN TBS has been done. Strategy for Pipe Forest maintenance has been coordinated with IO people.
Space arrangementSpace Arrangement Identification of CN TBS
CN TBS Integration with ITERCN TBS Integration with ITER
17
500kg Ingot of CLF-1
1-ton Ingot of CLF-1
3. Progress on R&D:3. Progress on R&D: Structural Materials-CLF-1
Consumable electrode furnace Two RAFM alloys are being developed in China; CLF and CLAMA 500kg and 1-ton ingots of CLF-1 steel were recently produced by vacuum induction melting and electro-slag remelting method. The optimization of the melting technique for the larger ingots to
is underway.
Tensile strength of CLF-1 DBTT of CLF-1
Remelting facility
18
3. Progress on R&D:3. Progress on R&D: Ceramic Breeder Pebbles
Relative density 94% TD
Li4SiO4 phase content 90%
Closed porosity 0.72%
Open porosity 5.2 %
Average crush load 7.0 N
Specific surface area 1.092 m2/gLi2TiO3 Pebbles (D=1mm)@CAEP
Li4SiO4 Pebbles (D=1mm) by
extrusion–sintering method @CIAE
Two kinds of ceramic breeders (Li4SiO4, Li2TiO3) for TBM are being developed at different institutions in China;
Lithium orthosilicate (Li4SiO4 ) pebbles will be the primary option in the CN HCCB TBM.
Li4SiO4 Pebbles (D=1mm)
by metl spraying method @SWIP Li4SiO4 Pebbles (D=1mm)
by freeze-sintering method @CAEP
Ceramic breeder (Li4SiO4) pebbles fabricated by melt spraying method have good sphericity, and high density.
Ceramic breeder (Li4SiO4) pebbles prepared by Freeze-sintering process have good mechanical properties (the average crush load is 50N) ;
Li2TiO3 Pebbles have good surface
feature by using sol-gel method.
XRD pattern of Li4SiO4 pebbles
Main properties (Li4SiO4) by melt spraying method
15 20 25 30 35 40 45 50 55 60 65 700
1000
2000
3000
4000
5000
Inte
rnsity (C
ounts
)
2
Li4SiO
4
Li2SiO
3
Li2CO
3
3. Progress on R&D:3. Progress on R&D: Fabrication of Be Pebbles
ChineseVHP-Be
Be BeO% Al C Fe Mg SiOther metallic
elements
1# ≥99% 0.750 0.006 0.060 0.050 0.003 0.009 <0.04
Be metal of high performance was developed in China .
Be pebbles have been produced by Rotating Electrode Process (REP) method in China. Related performance tests are on going.
A new project to develop higher quality Be pebbles in China is being implemented for the ITER project.
Main chemical composition of Chinese Be 1#
Be Pebbles (D=1mm)
Micrographs of Be Pebbles (D=1mm) REP Facility at HBSM Co.
Be (wt%) 98.3
BeO (wt%) 1.67
Al (ppm) 235
Si (ppm) 18
Mn (ppm) 58
Mg (ppm) ≤10
Co (ppm) ≤10
Sample of Be Pebbles(D=1mm)
Chemical Composition of Be pebble
3. Progress on R&D3. Progress on R&D: Helium Coolant Test Loop
Flow diagram of He Loop Layout of He Loop
The construction of a small He Test Loop to validate circulator technology will be completed soon.
- The He test loop has two impellers. It uses aerostatic bearings to avoid oil lubricating.
Flow diagram of small He loop
Parameters Maximum flow rate /kg-1s
Inlet pressure /MPa
Maximum pressure head /MPa He inlet/outlet temperature /℃
Circulator ~0.35 8 0.4 ~50/65
A prototyped Helium Test Loop to validate TBM components and design is also to be built in SWIP. The circulator will use magnetic bearings. The flow rate will up to 1.3kg/s.
3-D view of circulator Impeller of circulator
Cross-section view
Main parameters of circulator design
21
Fabrication of Key Components of He Test Loop
22
3. Progress on R&D:3. Progress on R&D: Fabrication Process of U-Shaped FWFabrication Process of U-Shaped FW
A small-sized mock-up (1:3) of U-shaped first wall is completed; Two kinds of fabrication method of U-shaped FW have been considered;
23
3. Progress on R&D:3. Progress on R&D: Fabrication of Small Sized Mock-up Fabrication of Small Sized Mock-up A full-sized mock-up with 2X2 sub-modules arrangement using the RAFM steel (CLF-1)
as structure material will be completed in this year.
4. TBS R&D and Delivery Plan4. TBS R&D and Delivery Plan
1. CN HCCB TBS qualification activities– Helium experimental loop (1:3) construction (2010.01-2011.06)– Conceptual design of CN HCCB TBM(2010.01-2012.12)– CN TBM testing and update design (2011.06-2013.12)– Preliminary design of CN HCCB TBM (2013.01-2013.12)– Prototype helium loop construction (2012.01-2014.06)– Large scale TBM mock-up tests (2014.06-2015.12)– Final design of CN HCCB TBM (2014.01-2015.12)
2. CN HCCB TBS delivery activities.– Main TBS components fabrication (2016.01-2017.06)
Final TBS design in ITER. Main TBS components fabrication. TBS function tests (domestic).
– CN TBS delivery (2016.12-2017.06)– CN TBS acceptance tests in ITER site (2017.06-2017.12)– EM TBM delivery (2018.01-2018.06)– EM-TBM System acceptance tests(2018.06-2019.06)
3. EM-TBM will be installed in ITER port after the first plasma shutdown (2019)24
High flux test reactor
25
Domestic and Intl. Cooperation Domestic and Intl. Cooperation
CAEP: China Academy of Engineering Physics; CIAE: China Institute of Atomic Energy;SJTU: Shanghai Jiao Tong University; ASIPP: Institute of Plasma Physics; Academy of Sciences ;NCEPU: North China Electric Power University; NECB: Nuclear Engineer Corporation , BeijingNPIC: Nuclear Power Institute, China; IMPCAS: Institute of Modern Physics, Chinese Academy of Sciences;TUINET: Tsinghua University, Institute of Nuclear Energy Technology; XJTU: Xi’an Jiao Tong University;SICCAS: Shanghai Institute of Ceramics, Chinese Academy of Sciences ; HBSMC: Haibao special metal materials Co.
SWIP CAEPCIAE ASIPPXJTU NCEPUNCIRD IMPCASNPIC TUINETSICCAS SJTU
SWIP CAEPCIAE ASIPPXJTU NCEPUNCIRD IMPCASNPIC TUINETSICCAS SJTU
Design Team R&D Team Safe & QA Team
SWIP CAEPCIAE SJTUASIPP NCEPUXJTU IMPCASNPIC TUINETSICCAS HBSMC
SWIP CAEPCIAE SJTUASIPP NCEPUXJTU IMPCASNPIC TUINETSICCAS HBSMC
SWIP CAEPCIAE NCEPUASIPP TUINETNPIC TUINETNCIRD SICCAS
SWIP CAEPCIAE NCEPUASIPP TUINETNPIC TUINETNCIRD SICCAS
CN HCCB TBMCN HCCB TBM
A lot of domestic units are joined into CN HCCB TBM program, including universities, institutes and industry company
CN HCCB TBM will be operated and tested on ITER through international cooperation under the frame of partnership with ITER parties.
China is interested in other TBM concepts as a partner in HCPB-TBM, WCCB-TBM and LiPb-based TBMs.
China HCCB TBM is open to cooperation with other ITER parties. Some informal discussions, for instance, CN-EU,CN-JA, CN-KO, has been started.
CN-US bilateral cooperation meeting on TBM program will held on Nov.7-9, 2011.
Intl. Cooperation and Partnership
Domestic and Intl. CooperationDomestic and Intl. Cooperation
5. Summary5. Summary
HCSB TBM with the Solid Breeder/Helium coolant/ RAFM material is the primary option of the Chinese TBM program.
Updated design, current progress on R&D, test and delivery plan up to the installation in ITER (2019) are presented.
Relevant R&D on key techniques for the HCSB TBM concept are supported by the Chinese ITER- DA domestic agency (2009-2012) , including:
– TBM optimization design and validation of key technologies;– Fabrication of Li4SiO4 pebbles and Be pebbles to large-scaled level;– Fabrication of structure material RAFM to ton level;– Construction of High Heat Flux Test Facility (Power:400kW);– Construction of small-scale and prototyped Helium Test Loop.
Testing HCSB TBM on ITER will be implemented with the cooperation of domestic and international institutions and industries.
Thanks for your Attention !Thanks for your Attention !
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